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Updating survival to incorporate harmonics branch.

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Adam Nelson 2014-06-27 06:49:06 -04:00
commit 2153223272
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162
docs/source/usersguide/input.rst
View file

@ -41,7 +41,7 @@ for the geometry, materials, and settings. Additionally, there are three optiona
input files. The first is a tallies XML file that specifies physical quantities
to be tallied. The second is a plots XML file that specifies regions of geometry
which should be plotted. The third is a CMFD XML file that specifies coarse mesh
acceleration geometry and execution parameters. OpenMC expects that these
acceleration geometry and execution parameters. OpenMC expects that these
files are called:
* ``geometry.xml``
@ -105,7 +105,7 @@ default. This element has the following attributes/sub-elements:
The ``<eigenvalue>`` element indicates that a :math:`k`-eigenvalue calculation
should be performed. It has the following attributes/sub-elements:
:batches:
:batches:
The total number of batches, where each batch corresponds to multiple
fission source iterations. Batching is done to eliminate correlation between
realizations of random variables.
@ -171,7 +171,7 @@ problem. It has the following attributes/sub-elements:
The ``<fixed_source>`` element indicates that a fixed source calculation should be
performed. It has the following attributes/sub-elements:
:batches:
:batches:
The total number of batches. For fixed source calculations, each batch
represents a realization of random variables for tallies.
@ -229,7 +229,7 @@ out the file and "false" will not.
*Default*: false
:summary:
:summary:
Writes out an ASCII summary file describing all of the user input files that
were read in.
@ -297,7 +297,7 @@ attributes/sub-elements:
An element specifying the spatial distribution of source sites. This element
has the following attributes:
:type:
:type:
The type of spatial distribution. Valid options are "box" and "point". A
"box" spatial distribution has coordinates sampled uniformly in a
parallelepiped. A "point" spatial distribution has coordinates specified
@ -321,7 +321,7 @@ attributes/sub-elements:
An element specifying the angular distribution of source sites. This element
has the following attributes:
:type:
:type:
The type of angular distribution. Valid options are "isotropic" and
"monodirectional". The angle of the particle emitted from a source site is
isotropic if the "isotropic" option is given. The angle of the particle
@ -344,7 +344,7 @@ attributes/sub-elements:
An element specifying the energy distribution of source sites. This element
has the following attributes:
:type:
:type:
The type of energy distribution. Valid options are "monoenergetic",
"watt", and "maxwell". The "monoenergetic" option produces source sites at
@ -373,8 +373,8 @@ attributes/sub-elements:
The ``<state_point>`` element indicates at what batches a state point file
should be written. A state point file can be used to restart a run or to get
tally results at any batch. The default behavior when using this tag is to
write out the source bank in the state_point file. This behavior can be
tally results at any batch. The default behavior when using this tag is to
write out the source bank in the state_point file. This behavior can be
customized by using the ``<source_point>`` element. This element has the
following attributes/sub-elements:
@ -394,8 +394,8 @@ following attributes/sub-elements:
``<source_point>`` Element
--------------------------
The ``<source_point>`` element indicates at what batches the source bank
should be written. The source bank can be either written out within a state
The ``<source_point>`` element indicates at what batches the source bank
should be written. The source bank can be either written out within a state
point file or separately in a source point file. This element has the following
attributes/sub-elements:
@ -425,17 +425,17 @@ attributes/sub-elements:
:source_write:
If this element is set to "false", source sites are not written
to the state point or source point file. This can substantially reduce the
to the state point or source point file. This can substantially reduce the
size of state points if large numbers of particles per batch are used.
*Default*: true
:overwrite_latest:
If this element is set to "true", a source point file containing
the source bank will be written out to a separate file named
``source.binary`` or ``source.h5`` depending on if HDF5 is enabled.
the source bank will be written out to a separate file named
``source.binary`` or ``source.h5`` depending on if HDF5 is enabled.
This file will be overwritten at every single batch so that the latest
source bank will be available. It should be noted that a user can set both
source bank will be available. It should be noted that a user can set both
this element to "true" and specify batches to write a permanent source bank.
*Default*: false
@ -879,7 +879,7 @@ The ``<tally>`` element accepts the following sub-elements:
:label:
This is an optional sub-element specifying the name of this tally to be used
for output purposes. This string is limited to 52 characters for formatting
for output purposes. This string is limited to 52 characters for formatting
purposes.
:filter:
@ -949,10 +949,11 @@ The ``<tally>`` element accepts the following sub-elements:
:scores:
A space-separated list of the desired responses to be accumulated. Accepted
options are "flux", "total", "scatter", "nu-scatter", "scatter-N",
"scatter-PN", "absorption", "fission", "nu-fission", "kappa-fission",
"current", and "events". These corresponding to the following physical
quantities.
options are "flux", "total", "scatter", "absorption", "fission",
"nu-fission", "kappa-fission", "nu-scatter", "scatter-N", "scatter-PN",
"scatter-YN", "nu-scatter-N", "nu-scatter-PN", "nu-scatter-YN", "flux-YN",
"total-YN", "current", and "events". These corresponding to the following
physical quantities:
:flux:
Total flux
@ -964,24 +965,6 @@ The ``<tally>`` element accepts the following sub-elements:
Total scattering rate. Can also be identified with the ``scatter-0``
response type.
:nu-scatter:
Total production of neutrons due to scattering. This accounts for
multiplicity from (n,2n), (n,3n), and (n,4n) reactions and should be
slightly higher than the scattering rate.
:scatter-N:
Tally the N\ :sup:`th` \ scattering moment, where N is the Legendre
expansion order. N must be between 0 and 10. As an example, tallying the
2\ :sup:`nd` \ scattering moment would be specified as ``<scores>
scatter-2 </scores>``.
:scatter-PN:
Tally all of the scattering moments from order 0 to N, where N is the
Legendre expansion order. That is, ``scatter-P1`` is equivalent to
requesting tallies of ``scatter-0`` and ``scatter-1``. N must be between
0 and 10. As an example, tallying up to the 2\ :sup:`nd` \ scattering
moment would be specified as ``<scores> scatter-P2 </scores>``.
:absorption:
Total absorption rate. This accounts for all reactions which do not
produce secondary neutrons.
@ -991,7 +974,7 @@ The ``<tally>`` element accepts the following sub-elements:
:nu-fission:
Total production of neutrons due to fission
:kappa-fission:
The recoverable energy production rate due to fission. The recoverable
energy is defined as the fission product kinetic energy, prompt and
@ -1001,6 +984,47 @@ The ``<tally>`` element accepts the following sub-elements:
prompt and delayed :math:`\gamma`-rays are assumed to deposit their energy
locally.
:scatter-N:
Tally the N\ :sup:`th` \ scattering moment, where N is the Legendre
expansion order of the change in particle angle :math:`\left(\mu\right)`.
N must be between 0 and 10. As an example, tallying the
2\ :sup:`nd` \ scattering moment would be specified as
``<scores> scatter-2 </scores>``.
:scatter-PN:
Tally all of the scattering moments from order 0 to N, where N is the
Legendre expansion order of the change in particle angle :math:`\left(\mu\right)`.
That is, ``scatter-P1`` is equivalent to requesting tallies of
``scatter-0`` and ``scatter-1``. Like for ``scatter-N``,
N must be between 0 and 10. As an example, tallying up to the
2\ :sup:`nd` \ scattering moment would be specified as
``<scores> scatter-P2 </scores>``.
:scatter-YN:
``scatter-YN`` is similar to ``scatter-PN`` except an additional
expansion is performed for the incoming particle direction
:math:`\left(\Omega\right)` using the real spherical harmonics. This is useful
for performing angular flux moment weighting of the scattering moments.
Like ``scatter-PN``, ``scatter-YN`` will tally all of the moments from
order 0 to N; N again must be between 0 and 10.
:nu-scatter, nu-scatter-N, nu-scatter-PN, nu-scatter-YN:
These scores are similar in functionality to their ``scatter*``
equivalents except the total production of neutrons due to
scattering is scored vice simply the scattering rate. This accounts for
multiplicity from (n,2n), (n,3n), and (n,4n) reactions.
:flux-YN:
Spherical harmonic expansion of the direction of motion
:math:`\left(\Omega\right)` of the total flux. This score will tally
all of the harmonic moments of order 0 to N. N must be between 0 and 10.
:total-YN:
Spherical harmonic expansion of the incoming particle's direction of
motion :math:`\left(\Omega\right)` of the total flux. This score will
tally all of the harmonic moments of order 0 to N. N must be between 0
and 10.
:current:
Partial currents on the boundaries of each cell in a mesh.
@ -1171,7 +1195,7 @@ attributes or sub-elements. These are not used in "voxel" plots:
Any number of this optional tag may be included in each ``<plot>`` element,
which can override the default random colors for cells or materials. Each
``col_spec`` element must contain ``id`` and ``rgb`` sub-elements.
:id:
Specifies the cell or material unique id for the color specification.
@ -1208,20 +1232,20 @@ attributes or sub-elements. These are not used in "voxel" plots:
------------------------------
CMFD Specification -- cmfd.xml
------------------------------
Coarse mesh finite difference acceleration method has been implemented in OpenMC.
Currently, it allows users to accelerate fission source convergence during
inactive neutron batches. To run CMFD, the ``<run_cmfd>`` element in
Currently, it allows users to accelerate fission source convergence during
inactive neutron batches. To run CMFD, the ``<run_cmfd>`` element in
``settings.xml`` should be set to "true".
``<active_flush>`` Element
--------------------------
The ``<active_flush>`` element controls the batch where CMFD tallies should be
reset. CMFD tallies should be reset before active batches so they are accumulated
reset. CMFD tallies should be reset before active batches so they are accumulated
without bias.
*Default*: 0
*Default*: 0
``<begin>`` Element
-------------------
@ -1258,9 +1282,9 @@ It can be turned on with "true" and off with "false".
``<inactive>`` Element
----------------------
The ``<inactive>`` element controls if cmfd tallies should be accumulated
during inactive batches. For some applications, CMFD tallies may not be
needed until the start of active batches. This option can be turned on
The ``<inactive>`` element controls if cmfd tallies should be accumulated
during inactive batches. For some applications, CMFD tallies may not be
needed until the start of active batches. This option can be turned on
with "true" and off with "false"
*Default*: true
@ -1277,12 +1301,12 @@ occurs. The amout of resets is controlled with the ``<num_flushes>`` element.
``<ksp_monitor>`` Element
-------------------------
The ``<ksp_monitor>`` element is used to view the convergence of linear GMRES
iterations in PETSc. This option can be turned on with "true" and turned off
The ``<ksp_monitor>`` element is used to view the convergence of linear GMRES
iterations in PETSc. This option can be turned on with "true" and turned off
with "false".
*Default*: false
*Default*: false
``<mesh>`` Element
------------------
@ -1295,7 +1319,7 @@ attributes/sub-elements:
given, it is assumed that the mesh is an x-y mesh.
:upper_right:
The upper-right corner of the structrued mesh. If only two coordinate are
The upper-right corner of the structrued mesh. If only two coordinate are
given, it is assumed that the mesh is an x-y mesh.
:dimension:
@ -1306,8 +1330,8 @@ attributes/sub-elements:
:energy:
Energy bins [in MeV], listed in ascending order (e.g. 0.0 0.625e-7 20.0)
for CMFD tallies and acceleration. If no energy bins are listed, OpenMC
automatically assumes a one energy group calculation over the entire
for CMFD tallies and acceleration. If no energy bins are listed, OpenMC
automatically assumes a one energy group calculation over the entire
energy range.
:albedo:
@ -1317,10 +1341,10 @@ attributes/sub-elements:
*Default*: 1.0 1.0 1.0 1.0 1.0 1.0
:map:
An optional acceleration map can be specified to overlay on the coarse
mesh spatial grid. If this option is used a ``1`` is used for a
An optional acceleration map can be specified to overlay on the coarse
mesh spatial grid. If this option is used a ``1`` is used for a
non-accelerated region and a ``2`` is used for an accelerated region.
For a simple 4x4 coarse mesh with a 2x2 fuel lattice surrounded by
For a simple 4x4 coarse mesh with a 2x2 fuel lattice surrounded by
reflector, the map is:
``1 1 1 1``
@ -1331,24 +1355,24 @@ attributes/sub-elements:
``1 1 1 1``
Therefore a 2x2 system of equations is solved rather than a 4x4. This
is extremely important to use in reflectors as neutrons will not
Therefore a 2x2 system of equations is solved rather than a 4x4. This
is extremely important to use in reflectors as neutrons will not
contribute to any tallies far away from fission source neutron regions.
A ``2`` must be used to identify any fission source region.
.. note:: Only two of the following three sub-elements are needed:
``lower_left``, ``upper_right`` and ``width``. Any combination
.. note:: Only two of the following three sub-elements are needed:
``lower_left``, ``upper_right`` and ``width``. Any combination
of two of these will yield the third.
``<norm>`` Element
------------------
The ``<norm>`` element is used to normalize the CMFD fission source distribution
to a particular value. For example, if a fission source is calculated for a
17 x 17 lattice of pins, the fission source may be normalized to the number of
fission source regions, in this case 289. This is useful when visualizing this
distribution as the average peaking factor will be unity. This parameter will
not impact the calculation.
The ``<norm>`` element is used to normalize the CMFD fission source distribution
to a particular value. For example, if a fission source is calculated for a
17 x 17 lattice of pins, the fission source may be normalized to the number of
fission source regions, in this case 289. This is useful when visualizing this
distribution as the average peaking factor will be unity. This parameter will
not impact the calculation.
*Default*: 1.0
@ -1363,7 +1387,7 @@ occur during inactive CMFD batches.
``<power_monitor>`` Element
---------------------------
The ``<power_monitor>`` element is used to view the convergence of power iteration.
The ``<power_monitor>`` element is used to view the convergence of power iteration.
This option can be turned on with "true" and turned off with "false".
*Default*: false
@ -1389,7 +1413,7 @@ function in PETSc. This option can be turned on with "true" and turned off with
--------------------
The ``<solver>`` element controls whether the CMFD eigenproblem is solved with
standard power iteration or nonlinear Jacobian-free Newton Krylov (JFNK).
standard power iteration or nonlinear Jacobian-free Newton Krylov (JFNK).
By setting "power", power iteration is used and by setting "jfnk", JFNK is used.
*Default*: power

30
src/cmfd_input.F90
View file

@ -8,7 +8,7 @@ module cmfd_input
implicit none
private
public :: configure_cmfd
public :: configure_cmfd
contains
@ -119,7 +119,7 @@ contains
cmfd % egrid = (/0.0_8,20.0_8/)
cmfd % indices(4) = 1 ! one energy group
end if
! Set global albedo
if (check_for_node(node_mesh, "albedo")) then
call get_node_array(node_mesh, "albedo", cmfd % albedo)
@ -134,7 +134,7 @@ contains
if (get_arraysize_integer(node_mesh, "map") /= &
product(cmfd % indices(1:3))) then
message = 'FATAL==>CMFD coremap not to correct dimensions'
call fatal_error()
call fatal_error()
end if
allocate(iarray(get_arraysize_integer(node_mesh, "map")))
call get_node_array(node_mesh, "map", iarray)
@ -206,7 +206,7 @@ contains
! Batch to begin cmfd
if (check_for_node(doc, "begin")) &
call get_node_value(doc, "begin", cmfd_begin)
call get_node_value(doc, "begin", cmfd_begin)
! Tally during inactive batches
if (check_for_node(doc, "inactive")) then
@ -288,7 +288,7 @@ contains
m => meshes(n_user_meshes+1)
! Set mesh id
m % id = n_user_meshes + 1
m % id = n_user_meshes + 1
! Set mesh type to rectangular
m % type = LATTICE_RECT
@ -422,7 +422,7 @@ contains
if (check_for_node(node_mesh, "energy")) then
n_filters = n_filters + 1
filters(n_filters) % type = FILTER_ENERGYIN
ng = get_arraysize_double(node_mesh, "energy")
ng = get_arraysize_double(node_mesh, "energy")
filters(n_filters) % n_bins = ng - 1
allocate(filters(n_filters) % real_bins(ng))
call get_node_array(node_mesh, "energy", &
@ -454,20 +454,20 @@ contains
allocate(t % filters(n_filters))
t % filters = filters(1:n_filters)
! Allocate scoring bins
! Allocate scoring bins
allocate(t % score_bins(3))
t % n_score_bins = 3
t % n_user_score_bins = 3
! Allocate scattering order data
allocate(t % scatt_order(3))
t % scatt_order = 0
allocate(t % moment_order(3))
t % moment_order = 0
! Set macro_bins
t % score_bins(1) = SCORE_FLUX
t % score_bins(2) = SCORE_TOTAL
t % score_bins(3) = SCORE_SCATTER_N
t % scatt_order(3) = 1
t % moment_order(3) = 1
else if (i == 2) then
@ -507,8 +507,8 @@ contains
t % n_user_score_bins = 2
! Allocate scattering order data
allocate(t % scatt_order(2))
t % scatt_order = 0
allocate(t % moment_order(2))
t % moment_order = 0
! Set macro_bins
t % score_bins(1) = SCORE_NU_SCATTER
@ -550,8 +550,8 @@ contains
t % n_user_score_bins = 1
! Allocate scattering order data
allocate(t % scatt_order(1))
t % scatt_order = 0
allocate(t % moment_order(1))
t % moment_order = 0
! Set macro bins
t % score_bins(1) = SCORE_CURRENT

43
src/constants.F90
View file

@ -11,7 +11,7 @@ module constants
integer, parameter :: VERSION_RELEASE = 4
! Revision numbers for binary files
integer, parameter :: REVISION_STATEPOINT = 11
integer, parameter :: REVISION_STATEPOINT = 12
integer, parameter :: REVISION_PARTICLE_RESTART = 1
! Binary file types
@ -276,7 +276,7 @@ module constants
EVENT_ABSORB = 2
! Tally score type
integer, parameter :: N_SCORE_TYPES = 14
integer, parameter :: N_SCORE_TYPES = 20
integer, parameter :: &
SCORE_FLUX = -1, & ! flux
SCORE_TOTAL = -2, & ! total reaction rate
@ -284,18 +284,37 @@ module constants
SCORE_NU_SCATTER = -4, & ! scattering production rate
SCORE_SCATTER_N = -5, & ! arbitrary scattering moment
SCORE_SCATTER_PN = -6, & ! system for scoring 0th through nth moment
SCORE_TRANSPORT = -7, & ! transport reaction rate
SCORE_N_1N = -8, & ! (n,1n) rate
SCORE_ABSORPTION = -9, & ! absorption rate
SCORE_FISSION = -10, & ! fission rate
SCORE_NU_FISSION = -11, & ! neutron production rate
SCORE_KAPPA_FISSION = -12, & ! fission energy production rate
SCORE_CURRENT = -13, & ! partial current
SCORE_EVENTS = -14 ! number of events
SCORE_NU_SCATTER_N = -7, & ! arbitrary nu-scattering moment
SCORE_NU_SCATTER_PN = -8, & ! system for scoring 0th through nth nu-scatter moment
SCORE_TRANSPORT = -9, & ! transport reaction rate
SCORE_N_1N = -10, & ! (n,1n) rate
SCORE_ABSORPTION = -11, & ! absorption rate
SCORE_FISSION = -12, & ! fission rate
SCORE_NU_FISSION = -13, & ! neutron production rate
SCORE_KAPPA_FISSION = -14, & ! fission energy production rate
SCORE_CURRENT = -15, & ! partial current
SCORE_FLUX_YN = -16, & ! angular moment of flux
SCORE_TOTAL_YN = -17, & ! angular moment of total reaction rate
SCORE_SCATTER_YN = -18, & ! angular flux-weighted scattering moment (0:N)
SCORE_NU_SCATTER_YN = -19, & ! angular flux-weighted nu-scattering moment (0:N)
SCORE_EVENTS = -20 ! number of events
! Maximum scattering order supported
integer, parameter :: SCATT_ORDER_MAX = 10
character(len=*), parameter :: SCATT_ORDER_MAX_PNSTR = "scatter-p10"
integer, parameter :: MAX_ANG_ORDER = 10
! Names of *-PN & *-YN scores (MOMENT_STRS) and *-N moment scores
character(*), parameter :: &
MOMENT_STRS(6) = (/ "scatter-p ", &
"nu-scatter-p", &
"flux-y ", &
"total-y ", &
"scatter-y ", &
"nu-scatter-y"/), &
MOMENT_N_STRS(2) = (/ "scatter- ", &
"nu-scatter- "/)
! Location in MOMENT_STRS where the YN data begins
integer, parameter :: YN_LOC = 3
! Tally map bin finding
integer, parameter :: NO_BIN_FOUND = -1

303
src/input_xml.F90
View file

@ -185,7 +185,7 @@ contains
! If the number of particles was specified as a command-line argument, we
! don't set it here
if (n_particles == 0) n_particles = temp_long
if (n_particles == 0) n_particles = temp_long
! Copy batch information
call get_node_value(node_mode, "batches", n_batches)
@ -278,10 +278,10 @@ contains
else
! Spatial distribution for external source
if (check_for_node(node_source, "space")) then
if (check_for_node(node_source, "space")) then
! Get pointer to spatial distribution
call get_node_ptr(node_source, "space", node_dist)
call get_node_ptr(node_source, "space", node_dist)
! Check for type of spatial distribution
type = ''
@ -624,7 +624,7 @@ contains
elseif (check_for_node(node_sp, "interval")) then
! User gave an interval for writing state points
call get_node_value(node_sp, "interval", temp_int)
n_state_points = n_batches / temp_int
n_state_points = n_batches / temp_int
do i = 1, n_state_points
call statepoint_batch % add(temp_int * i)
end do
@ -648,7 +648,7 @@ contains
! Determine number of batches at which to store source points
if (check_for_node(node_sp, "batches")) then
n_source_points = get_arraysize_integer(node_sp, "batches")
n_source_points = get_arraysize_integer(node_sp, "batches")
else
n_source_points = 0
end if
@ -700,7 +700,7 @@ contains
end if
else
! If no <source_point> tag was present, by default we keep source bank in
! statepoint file and write it out at statepoints intervals
! statepoint file and write it out at statepoints intervals
source_separate = .false.
n_source_points = n_state_points
do i = 1, n_state_points
@ -944,7 +944,7 @@ contains
! Check to make sure that either material or fill was specified
if (c % material == NONE .and. c % fill == NONE) then
message = "Neither material nor fill was specified for cell " // &
message = "Neither material nor fill was specified for cell " // &
trim(to_str(c % id))
call fatal_error()
end if
@ -1139,7 +1139,7 @@ contains
n = get_arraysize_double(node_surf, "coeffs")
if (n < coeffs_reqd) then
message = "Not enough coefficients specified for surface: " // &
message = "Not enough coefficients specified for surface: " // &
trim(to_str(s % id))
call fatal_error()
elseif (n > coeffs_reqd) then
@ -1615,7 +1615,7 @@ contains
! Check to make sure cross-section is continuous energy neutron table
n = len_trim(name)
if (name(n:n) /= 'c') then
message = "Cross-section table " // trim(name) // &
message = "Cross-section table " // trim(name) // &
" is not a continuous-energy neutron table."
call fatal_error()
end if
@ -1644,7 +1644,7 @@ contains
! Check to make sure either all atom percents or all weight percents are
! given
if (.not. (all(mat % atom_density > ZERO) .or. &
if (.not. (all(mat % atom_density > ZERO) .or. &
all(mat % atom_density < ZERO))) then
message = "Cannot mix atom and weight percents in material " // &
to_str(mat % id)
@ -1745,12 +1745,14 @@ contains
integer :: n ! size of arrays in mesh specification
integer :: n_words ! number of words read
integer :: n_filters ! number of filters
integer :: n_new ! number of new scores to add based on Pn tally
integer :: n_scores ! number of tot scores after adjusting for Pn tally
integer :: n_order ! Scattering order requested
integer :: n_new ! number of new scores to add based on Yn/Pn tally
integer :: n_scores ! number of tot scores after adjusting for Yn/Pn tally
integer :: n_bins ! Total new bins for this score
integer :: n_order ! Moment order requested
integer :: n_order_pos ! Position of Scattering order in score name string
integer :: MT ! user-specified MT for score
integer :: iarray3(3) ! temporary integer array
integer :: imomstr ! Index of MOMENT_STRS & MOMENT_N_STRS
logical :: file_exists ! does tallies.xml file exist?
real(8) :: rarray3(3) ! temporary double prec. array
character(MAX_LINE_LEN) :: filename
@ -2168,7 +2170,7 @@ contains
case default
! Specified tally filter is invalid, raise error
message = "Unknown filter type '" // &
message = "Unknown filter type '" // &
trim(temp_str) // "' on tally " // &
trim(to_str(t % id)) // "."
call fatal_error()
@ -2220,7 +2222,7 @@ contains
t % all_nuclides = .true.
else
! Any other case, e.g. <nuclides>U-235 Pu-239</nuclides>
n_words = get_arraysize_string(node_tal, "nuclides")
n_words = get_arraysize_string(node_tal, "nuclides")
allocate(t % nuclide_bins(n_words))
do j = 1, n_words
! Check if total material was specified
@ -2242,7 +2244,7 @@ contains
word = pair_list % key(1:150)
exit
end if
! Advance to next
pair_list => pair_list % next
end do
@ -2291,79 +2293,110 @@ contains
! READ DATA FOR SCORES
if (check_for_node(node_tal, "scores")) then
! Loop through scores and determine if a scatter-p# input was used
! to allow for proper pre-allocating of t % score_bins
! This scheme allows multiple scatter-p# to be requested by the user
! if so desired
n_words = get_arraysize_string(node_tal, "scores")
allocate(sarray(n_words))
call get_node_array(node_tal, "scores", sarray)
! Before we can allocate storage for scores, we must determine the
! number of additional scores required due to the moment scores
! (i.e., scatter-p#, flux-y#)
n_new = 0
do j = 1, n_words
call lower_case(sarray(j))
! Find if scores(j) is of the form 'scatter-p'
! If so, get the number and do a select case on that.
! Find if scores(j) is of the form 'moment-p' or 'moment-y' present in
! MOMENT_STRS(:)
! If so, check the order, store if OK, then reset the number to 'n'
score_name = trim(sarray(j))
if (starts_with(score_name,'scatter-p')) then
n_order_pos = scan(score_name,'0123456789')
n_order = int(str_to_int( &
score_name(n_order_pos:(len_trim(score_name)))),4)
if (n_order > SCATT_ORDER_MAX) then
! Throw a warning. Set to the maximum number.
! The above scheme will essentially take the absolute value
message = "Invalid scattering order of " // trim(to_str(n_order)) // &
" requested. Setting to the maximum permissible value, " // &
trim(to_str(SCATT_ORDER_MAX))
call warning()
n_order = SCATT_ORDER_MAX
sarray(j) = SCATT_ORDER_MAX_PNSTR
do imomstr = 1, size(MOMENT_STRS)
if (starts_with(score_name,trim(MOMENT_STRS(imomstr)))) then
n_order_pos = scan(score_name,'0123456789')
n_order = int(str_to_int( &
score_name(n_order_pos:(len_trim(score_name)))),4)
if (n_order > MAX_ANG_ORDER) then
! User requested too many orders; throw a warning and set to the
! maximum order.
! The above scheme will essentially take the absolute value
message = "Invalid scattering order of " // trim(to_str(n_order)) // &
" requested. Setting to the maximum permissible value, " // &
trim(to_str(MAX_ANG_ORDER))
call warning()
n_order = MAX_ANG_ORDER
sarray(j) = trim(MOMENT_STRS(imomstr)) // &
trim(to_str(MAX_ANG_ORDER))
end if
! Find total number of bins for this case
if (imomstr >= YN_LOC) then
n_bins = (n_order + 1)**2
else
n_bins = n_order + 1
end if
! We subtract one since n_words already included
n_new = n_new + n_bins - 1
exit
end if
n_new = n_new + n_order
end if
end do
end do
n_scores = n_words + n_new
! Allocate accordingly
! Allocate score storage accordingly
allocate(t % score_bins(n_scores))
allocate(t % scatt_order(n_scores))
t % scatt_order = 0
allocate(t % moment_order(n_scores))
t % moment_order = 0
j = 0
do l = 1, n_words
j = j + 1
! Get the input string in scores(l) but if scatter-n or scatter-pn
! then strip off the n, and store it as an integer to be used later
! Peform the select case on this modified (number removed) string
! Get the input string in scores(l) but if score is one of the moment
! scores then strip off the n and store it as an integer to be used
! later. Then perform the select case on this modified (number removed) string
score_name = sarray(l)
if (starts_with(score_name,'scatter-p')) then
n_order_pos = scan(score_name,'0123456789')
n_order = int(str_to_int( &
score_name(n_order_pos:(len_trim(score_name)))),4)
if (n_order > SCATT_ORDER_MAX) then
! Throw a warning. Set to the maximum number.
! The above scheme will essentially take the absolute value
message = "Invalid scattering order of " // trim(to_str(n_order)) // &
" requested. Setting to the maximum permissible value, " // &
trim(to_str(SCATT_ORDER_MAX))
call warning()
n_order = SCATT_ORDER_MAX
do imomstr = 1, size(MOMENT_STRS)
if (starts_with(score_name,trim(MOMENT_STRS(imomstr)))) then
n_order_pos = scan(score_name,'0123456789')
n_order = int(str_to_int( &
score_name(n_order_pos:(len_trim(score_name)))),4)
if (n_order > MAX_ANG_ORDER) then
! User requested too many orders; throw a warning and set to the
! maximum order.
! The above scheme will essentially take the absolute value
message = "Invalid scattering order of " // trim(to_str(n_order)) // &
" requested. Setting to the maximum permissible value, " // &
trim(to_str(MAX_ANG_ORDER))
call warning()
n_order = MAX_ANG_ORDER
end if
score_name = trim(MOMENT_STRS(imomstr)) // "n"
! Find total number of bins for this case
if (imomstr >= YN_LOC) then
n_bins = (n_order + 1)**2
else
n_bins = n_order + 1
end if
exit
end if
score_name = "scatter-pn"
else if (starts_with(score_name,'scatter-')) then
n_order_pos = scan(score_name,'0123456789')
n_order = int(str_to_int( &
score_name(n_order_pos:(len_trim(score_name)))),4)
if (n_order > SCATT_ORDER_MAX) then
! Throw a warning. Set to the maximum number.
! The above scheme will essentially take the absolute value
message = "Invalid scattering order of " // trim(to_str(n_order)) // &
" requested. Setting to the maximum permissible value, " // &
trim(to_str(SCATT_ORDER_MAX))
call warning()
n_order = SCATT_ORDER_MAX
end if
score_name = "scatter-n"
end do
! Now check the Moment_N_Strs, but only if we werent successful above
if (imomstr > size(MOMENT_STRS)) then
do imomstr = 1, size(MOMENT_N_STRS)
if (starts_with(score_name,trim(MOMENT_N_STRS(imomstr)))) then
n_order_pos = scan(score_name,'0123456789')
n_order = int(str_to_int( &
score_name(n_order_pos:(len_trim(score_name)))),4)
if (n_order > MAX_ANG_ORDER) then
! User requested too many orders; throw a warning and set to the
! maximum order.
! The above scheme will essentially take the absolute value
message = "Invalid scattering order of " // trim(to_str(n_order)) // &
" requested. Setting to the maximum permissible value, " // &
trim(to_str(MAX_ANG_ORDER))
call warning()
n_order = MAX_ANG_ORDER
end if
score_name = trim(MOMENT_N_STRS(imomstr)) // "n"
exit
end if
end do
end if
select case (trim(score_name))
case ('flux')
! Prohibit user from tallying flux for an individual nuclide
@ -2378,6 +2411,23 @@ contains
message = "Cannot tally flux with an outgoing energy filter."
call fatal_error()
end if
case ('flux-yn')
! Prohibit user from tallying flux for an individual nuclide
if (.not. (t % n_nuclide_bins == 1 .and. &
t % nuclide_bins(1) == -1)) then
message = "Cannot tally flux for an individual nuclide."
call fatal_error()
end if
if (t % find_filter(FILTER_ENERGYOUT) > 0) then
message = "Cannot tally flux with an outgoing energy filter."
call fatal_error()
end if
t % score_bins(j : j + n_bins - 1) = SCORE_FLUX_YN
t % moment_order(j : j + n_bins - 1) = n_order
j = j + n_bins - 1
case ('total')
t % score_bins(j) = SCORE_TOTAL
if (t % find_filter(FILTER_ENERGYOUT) > 0) then
@ -2385,9 +2435,21 @@ contains
&outgoing energy filter."
call fatal_error()
end if
case ('total-yn')
if (t % find_filter(FILTER_ENERGYOUT) > 0) then
message = "Cannot tally total reaction rate with an &
&outgoing energy filter."
call fatal_error()
end if
t % score_bins(j : j + n_bins - 1) = SCORE_TOTAL_YN
t % moment_order(j : j + n_bins - 1) = n_order
j = j + n_bins - 1
case ('scatter')
t % score_bins(j) = SCORE_SCATTER
case ('nu-scatter')
t % score_bins(j) = SCORE_NU_SCATTER
@ -2401,22 +2463,53 @@ contains
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
end if
t % scatt_order(j) = n_order
t % moment_order(j) = n_order
case ('nu-scatter-n')
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
if (n_order == 0) then
t % score_bins(j) = SCORE_NU_SCATTER
else
t % score_bins(j) = SCORE_NU_SCATTER_N
end if
t % moment_order(j) = n_order
case ('scatter-pn')
t % estimator = ESTIMATOR_ANALOG
! Setup P0:Pn
t % score_bins(j : j + n_order) = SCORE_SCATTER_PN
t % scatt_order(j : j + n_order) = n_order
j = j + n_order
t % score_bins(j : j + n_bins - 1) = SCORE_SCATTER_PN
t % moment_order(j : j + n_bins - 1) = n_order
j = j + n_bins - 1
case ('nu-scatter-pn')
t % estimator = ESTIMATOR_ANALOG
! Setup P0:Pn
t % score_bins(j : j + n_bins - 1) = SCORE_NU_SCATTER_PN
t % moment_order(j : j + n_bins - 1) = n_order
j = j + n_bins - 1
case ('scatter-yn')
t % estimator = ESTIMATOR_ANALOG
! Setup P0:Pn
t % score_bins(j : j + n_bins - 1) = SCORE_SCATTER_YN
t % moment_order(j : j + n_bins - 1) = n_order
j = j + n_bins - 1
case ('nu-scatter-yn')
t % estimator = ESTIMATOR_ANALOG
! Setup P0:Pn
t % score_bins(j : j + n_bins - 1) = SCORE_NU_SCATTER_YN
t % moment_order(j : j + n_bins - 1) = n_order
j = j + n_bins - 1
case('transport')
t % score_bins(j) = SCORE_TRANSPORT
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
case ('diffusion')
message = "Diffusion score no longer supported for tallies, &
message = "Diffusion score no longer supported for tallies, &
&please remove"
call fatal_error()
case ('n1n')
@ -2519,14 +2612,14 @@ contains
t % score_bins(j) = MT
else
message = "Invalid MT on <scores>: " // &
trim(sarray(j))
trim(sarray(l))
call fatal_error()
end if
else
! Specified score was not an integer
message = "Unknown scoring function: " // &
trim(sarray(j))
trim(sarray(l))
call fatal_error()
end if
@ -2675,7 +2768,7 @@ contains
pl % path_plot = trim(path_input) // trim(to_str(pl % id)) // &
"_" // trim(filename) // ".voxel"
end select
! Copy plot pixel size
if (pl % type == PLOT_TYPE_SLICE) then
if (get_arraysize_integer(node_plot, "pixels") == 2) then
@ -2698,7 +2791,7 @@ contains
! Copy plot background color
if (check_for_node(node_plot, "background")) then
if (pl % type == PLOT_TYPE_VOXEL) then
message = "Background color ignored in voxel plot " // &
message = "Background color ignored in voxel plot " // &
trim(to_str(pl % id))
call warning()
end if
@ -2712,7 +2805,7 @@ contains
else
pl % not_found % rgb = (/ 255, 255, 255 /)
end if
! Copy plot basis
if (pl % type == PLOT_TYPE_SLICE) then
temp_str = 'xy'
@ -2727,12 +2820,12 @@ contains
case ("yz")
pl % basis = PLOT_BASIS_YZ
case default
message = "Unsupported plot basis '" // trim(temp_str) &
message = "Unsupported plot basis '" // trim(temp_str) &
// "' in plot " // trim(to_str(pl % id))
call fatal_error()
end select
end if
! Copy plotting origin
if (get_arraysize_double(node_plot, "origin") == 3) then
call get_node_array(node_plot, "origin", pl % origin)
@ -2799,13 +2892,13 @@ contains
! Copy user specified colors
if (n_cols /= 0) then
if (pl % type == PLOT_TYPE_VOXEL) then
message = "Color specifications ignored in voxel plot " // &
message = "Color specifications ignored in voxel plot " // &
trim(to_str(pl % id))
call warning()
end if
do j = 1, n_cols
! Get pointer to color spec XML node
@ -2815,7 +2908,7 @@ contains
if (get_arraysize_double(node_col, "rgb") /= 3) then
message = "Bad RGB " &
// "in plot " // trim(to_str(pl % id))
call fatal_error()
call fatal_error()
end if
! Ensure that there is an id for this color specification
@ -2858,13 +2951,13 @@ contains
call get_node_list(node_plot, "mask", node_mask_list)
n_masks = get_list_size(node_mask_list)
if (n_masks /= 0) then
if (pl % type == PLOT_TYPE_VOXEL) then
message = "Mask ignored in voxel plot " // &
message = "Mask ignored in voxel plot " // &
trim(to_str(pl % id))
call warning()
end if
select case(n_masks)
case default
message = "Mutliple masks" // &
@ -2885,14 +2978,14 @@ contains
end if
allocate(iarray(n_comp))
call get_node_array(node_mask, "components", iarray)
! First we need to change the user-specified identifiers to indices
! in the cell and material arrays
do j=1, n_comp
col_id = iarray(j)
if (pl % color_by == PLOT_COLOR_CELLS) then
if (cell_dict % has_key(col_id)) then
iarray(j) = cell_dict % get_key(col_id)
else
@ -2900,9 +2993,9 @@ contains
" specified in the mask in plot " // trim(to_str(pl % id))
call fatal_error()
end if
else if (pl % color_by == PLOT_COLOR_MATS) then
if (material_dict % has_key(col_id)) then
iarray(j) = material_dict % get_key(col_id)
else
@ -2910,10 +3003,10 @@ contains
" specified in the mask in plot " // trim(to_str(pl % id))
call fatal_error()
end if
end if
end if
end do
! Alter colors based on mask information
do j=1,size(pl % colors)
if (.not. any(j .eq. iarray)) then
@ -2928,9 +3021,9 @@ contains
end do
deallocate(iarray)
end select
end if
! Add plot to dictionary
@ -2970,7 +3063,7 @@ contains
"' does not exist!"
call fatal_error()
end if
message = "Reading cross sections XML file..."
call write_message(5)

400
src/math.F90
View file

@ -1,6 +1,6 @@
module math
use constants, only: PI, ONE, TWO
use constants, only: PI, ONE, TWO, ZERO
use random_lcg, only: prn
implicit none
@ -116,20 +116,20 @@ contains
!===============================================================================
! CALC_PN calculates the n-th order Legendre polynomial at the value of x.
! Since this function is called repeatedly during the neutron transport process,
! neither n or x is checked to see if they are in the applicable range.
! neither n or x is checked to see if they are in the applicable range.
! This is left to the client developer to use where applicable. x is to be in
! the domain of [-1,1], and 0<=n<=5. If x is outside of the range, the return
! value will be outside the expected range; if n is outside the stated range,
! value will be outside the expected range; if n is outside the stated range,
! the return value will be 1.0.
!===============================================================================
pure function calc_pn(n,x) result(pnx)
integer, intent(in) :: n ! Legendre order requested
real(8), intent(in) :: x ! Independent variable the Legendre is to be
real(8), intent(in) :: x ! Independent variable the Legendre is to be
! evaluated at; x must be in the domain [-1,1]
real(8) :: pnx ! The Legendre poly of order n evaluated at x
select case(n)
case(1)
pnx = x
@ -144,7 +144,7 @@ contains
case(6)
pnx = 14.4375_8 * (x ** 6) - 19.6875_8 * (x ** 4) + &
6.5625_8 * x * x - 0.3125_8
case(7)
case(7)
pnx = 26.8125_8 * (x ** 7) - 43.3125_8 * (x ** 5) + &
19.6875_8 * x * x * x - 2.1875_8 * x
case(8)
@ -160,9 +160,393 @@ contains
case default
pnx = ONE ! correct for case(0), incorrect for the rest
end select
end function calc_pn
!===============================================================================
! CALC_RN calculates the n-th order spherical harmonics for a given angle
! (in terms of (u,v,w)). All Rn,m values are provided (where -n<=m<=n)
!===============================================================================
pure function calc_rn(n,uvw) result(rn)
integer, intent(in) :: n ! Order requested
real(8), intent(in) :: uvw(3) ! Direction of travel, assumed to be on unit sphere
real(8) :: rn(2*n + 1) ! The resultant R_n(uvw)
real(8) :: phi, w ! Azimuthal and Cosine of Polar angles (from uvw)
real(8) :: w2m1 ! (w^2 - 1), frequently used in these
w = uvw(3) ! z = cos(polar)
if (uvw(1) == ZERO) then
phi = ZERO
else
! phi = atan(uvw(2) / uvw(1))
phi = atan2(uvw(2), uvw(1))
end if
w2m1 = (ONE - w**2)
select case(n)
case (0)
! l = 0, m = 0
rn(1) = ONE
case (1)
! l = 1, m = -1
rn(1) = ONE*sqrt(w2m1) * sin(phi)
! l = 1, m = 0
rn(2) = ONE * w
! l = 1, m = 1
rn(3) = ONE*sqrt(w2m1) * cos(phi)
case (2)
! l = 2, m = -2
rn(1) = 0.288675134594813_8 * (-3.0_8 * w**2 + 3.0_8) * sin(TWO*phi)
! l = 2, m = -1
rn(2) = 1.73205080756888_8 * w*sqrt(w2m1) * sin(phi)
! l = 2, m = 0
rn(3) = 1.5_8 * w**2 - 0.5_8
! l = 2, m = 1
rn(4) = 1.73205080756888_8 * w*sqrt(w2m1) * cos(phi)
! l = 2, m = 2
rn(5) = 0.288675134594813_8 * (-3.0_8 * w**2 + 3.0_8) * cos(TWO*phi)
case (3)
! l = 3, m = -3
rn(1) = 0.790569415042095_8 * (w2m1)**(3.0_8/TWO) * sin(3.0_8 * phi)
! l = 3, m = -2
rn(2) = 1.93649167310371_8 * w*(w2m1) * sin(TWO*phi)
! l = 3, m = -1
rn(3) = 0.408248290463863_8*sqrt(w2m1)*((15.0_8/TWO)*w**2 - 3.0_8/TWO) * &
sin(phi)
! l = 3, m = 0
rn(4) = 2.5_8 * w**3 - 1.5_8 * w
! l = 3, m = 1
rn(5) = 0.408248290463863_8*sqrt(w2m1)*((15.0_8/TWO)*w**2 - 3.0_8/TWO) * &
cos(phi)
! l = 3, m = 2
rn(6) = 1.93649167310371_8 * w*(w2m1) * cos(TWO*phi)
! l = 3, m = 3
rn(7) = 0.790569415042095_8 * (w2m1)**(3.0_8/TWO) * cos(3.0_8* phi)
case (4)
! l = 4, m = -4
rn(1) = 0.739509972887452_8 * (w2m1)**2 * sin(4.0_8*phi)
! l = 4, m = -3
rn(2) = 2.09165006633519_8 * w*(w2m1)**(3.0_8/TWO) * sin(3.0_8* phi)
! l = 4, m = -2
rn(3) = 0.074535599249993_8 * (w2m1)*((105.0_8/TWO)*w**2 - 15.0_8/TWO) * &
sin(TWO*phi)
! l = 4, m = -1
rn(4) = 0.316227766016838_8*sqrt(w2m1)*((35.0_8/TWO)*w**3 - 15.0_8/TWO*w) * &
sin(phi)
! l = 4, m = 0
rn(5) = 4.375_8 * w**4 - 3.75_8 * w**2 + 0.375_8
! l = 4, m = 1
rn(6) = 0.316227766016838_8*sqrt(w2m1)*((35.0_8/TWO)*w**3 - 15.0_8/TWO*w) * &
cos(phi)
! l = 4, m = 2
rn(7) = 0.074535599249993_8 * (w2m1)*((105.0_8/TWO)*w**2 - 15.0_8/TWO) * &
cos(TWO*phi)
! l = 4, m = 3
rn(8) = 2.09165006633519_8 * w*(w2m1)**(3.0_8/TWO) * cos(3.0_8* phi)
! l = 4, m = 4
rn(9) = 0.739509972887452_8 * (w2m1)**2 * cos(4.0_8*phi)
case (5)
! l = 5, m = -5
rn(1) = 0.701560760020114_8 * (w2m1)**(5.0_8/TWO) * sin(5.0_8*phi)
! l = 5, m = -4
rn(2) = 2.21852991866236_8 * w*(w2m1)**2 * sin(4.0_8*phi)
! l = 5, m = -3
rn(3) = 0.00996023841111995_8 * (w2m1)**(3.0_8/TWO)* &
((945.0_8 /TWO)*w**2 - 105.0_8/TWO) * sin(3.0_8*phi)
! l = 5, m = -2
rn(4) = 0.0487950036474267_8 * (w2m1)*((315.0_8/TWO)*w**3 - 105.0_8/TWO*w) * &
sin(TWO*phi)
! l = 5, m = -1
rn(5) = 0.258198889747161_8*sqrt(w2m1)* &
((315.0_8/8.0_8)*w**4 - 105.0_8/4.0_8 * w**2 + 15.0_8/8.0_8) * sin(phi)
! l = 5, m = 0
rn(6) = 7.875_8 * w**5 - 8.75_8 * w**3 + 1.875_8 * w
! l = 5, m = 1
rn(7) = 0.258198889747161_8*sqrt(w2m1)* &
((315.0_8/8.0_8)*w**4 - 105.0_8/4.0_8 * w**2 + 15.0_8/8.0_8) * cos(phi)
! l = 5, m = 2
rn(8) = 0.0487950036474267_8 * (w2m1)* &
((315.0_8/TWO)*w**3 - 105.0_8/TWO*w) * cos(TWO*phi)
! l = 5, m = 3
rn(9) = 0.00996023841111995_8 * (w2m1)**(3.0_8/TWO)* &
((945.0_8 /TWO)*w**2 - 105.0_8/TWO) * cos(3.0_8*phi)
! l = 5, m = 4
rn(10) = 2.21852991866236_8 * w*(w2m1)**2 * cos(4.0_8*phi)
! l = 5, m = 5
rn(11) = 0.701560760020114_8 * (w2m1)**(5.0_8/TWO) * cos(5.0_8* phi)
case (6)
! l = 6, m = -6
rn(1) = 0.671693289381396_8 * (w2m1)**3 * sin(6.0_8*phi)
! l = 6, m = -5
rn(2) = 2.32681380862329_8 * w*(w2m1)**(5.0_8/TWO) * sin(5.0_8*phi)
! l = 6, m = -4
rn(3) = 0.00104990131391452_8 * (w2m1)**2 * &
((10395.0_8/TWO)*w**2 - 945.0_8/TWO) * sin(4.0_8*phi)
! l = 6, m = -3
rn(4) = 0.00575054632785295_8 * (w2m1)**(3.0_8/TWO) * &
((3465.0_8/TWO)*w**3 - 945.0_8/TWO*w) * sin(3.0_8*phi)
! l = 6, m = -2
rn(5) = 0.0345032779671177_8 * (w2m1) * &
((3465.0_8/8.0_8)*w**4 - 945.0_8/4.0_8 * w**2 + 105.0_8/8.0_8) * sin(TWO*phi)
! l = 6, m = -1
rn(6) = 0.218217890235992_8*sqrt(w2m1) * &
((693.0_8/8.0_8)*w**5- 315.0_8/4.0_8 * w**3 + (105.0_8/8.0_8)*w) * sin(phi)
! l = 6, m = 0
rn(7) = 14.4375_8 * w**6 - 19.6875_8 * w**4 + 6.5625_8 * w**2 - 0.3125_8
! l = 6, m = 1
rn(8) = 0.218217890235992_8*sqrt(w2m1) * &
((693.0_8/8.0_8)*w**5- 315.0_8/4.0_8 * w**3 + (105.0_8/8.0_8)*w) * cos(phi)
! l = 6, m = 2
rn(9) = 0.0345032779671177_8 * (w2m1) * &
((3465.0_8/8.0_8)*w**4 -945.0_8/4.0_8 * w**2 + 105.0_8/8.0_8) * cos(TWO*phi)
! l = 6, m = 3
rn(10) = 0.00575054632785295_8 * (w2m1)**(3.0_8/TWO) * &
((3465.0_8/TWO)*w**3 - 945.0_8/TWO*w) * cos(3.0_8*phi)
! l = 6, m = 4
rn(11) = 0.00104990131391452_8 * (w2m1)**2 * &
((10395.0_8/TWO)*w**2 - 945.0_8/TWO) * cos(4.0_8*phi)
! l = 6, m = 5
rn(12) = 2.32681380862329_8 * w*(w2m1)**(5.0_8/TWO) * cos(5.0_8*phi)
! l = 6, m = 6
rn(13) = 0.671693289381396_8 * (w2m1)**3 * cos(6.0_8*phi)
case (7)
! l = 7, m = -7
rn(1) = 0.647259849287749_8 * (w2m1)**(7.0_8/TWO) * sin(7.0_8*phi)
! l = 7, m = -6
rn(2) = 2.42182459624969_8 * w*(w2m1)**3 * sin(6.0_8*phi)
! l = 7, m = -5
rn(3) = 9.13821798555235d-5*(w2m1)**(5.0_8/TWO)* &
((135135.0_8/TWO)*w**2 - 10395.0_8/TWO) * sin(5.0_8*phi)
! l = 7, m = -4
rn(4) = 0.000548293079133141_8 * (w2m1)**2* &
((45045.0_8/TWO)*w**3 - 10395.0_8/TWO*w) * sin(4.0_8*phi)
! l = 7, m = -3
rn(5) = 0.00363696483726654_8 * (w2m1)**(3.0_8/TWO)* &
((45045.0_8/8.0_8)*w**4 - 10395.0_8/4.0_8 * w**2 + 945.0_8/8.0_8)* &
sin(3.0_8*phi)
! l = 7, m = -2
rn(6) = 0.025717224993682_8 * (w2m1)* &
((9009.0_8/8.0_8)*w**5 -3465.0_8/4.0_8 * w**3 + (945.0_8/8.0_8)*w)* &
sin(TWO*phi)
! l = 7, m = -1
rn(7) = 0.188982236504614_8*sqrt(w2m1)* &
((3003.0_8/16.0_8)*w**6 - 3465.0_8/16.0_8 * w**4 + &
(945.0_8/16.0_8)*w**2 - 35.0_8/16.0_8) * sin(phi)
! l = 7, m = 0
rn(8) = 26.8125_8 * w**7 - 43.3125_8 * w**5 + 19.6875_8 * w**3 -2.1875_8 * w
! l = 7, m = 1
rn(9) = 0.188982236504614_8*sqrt(w2m1)* &
((3003.0_8/16.0_8)*w**6 - 3465.0_8/16.0_8 * w**4 + &
(945.0_8/16.0_8)*w**2 - 35.0_8/16.0_8) * cos(phi)
! l = 7, m = 2
rn(10) = 0.025717224993682_8 * (w2m1)* &
((9009.0_8/8.0_8)*w**5 -3465.0_8/4.0_8 * w**3 + (945.0_8/8.0_8)*w)* &
cos(TWO*phi)
! l = 7, m = 3
rn(11) = 0.00363696483726654_8 * (w2m1)**(3.0_8/TWO)* &
((45045.0_8/8.0_8)*w**4 - 10395.0_8/4.0_8 * w**2 + 945.0_8/8.0_8)* &
cos(3.0_8*phi)
! l = 7, m = 4
rn(12) = 0.000548293079133141_8 * (w2m1)**2 * &
((45045.0_8/TWO)*w**3 - 10395.0_8/TWO*w) * cos(4.0_8*phi)
! l = 7, m = 5
rn(13) = 9.13821798555235d-5*(w2m1)**(5.0_8/TWO)* &
((135135.0_8/TWO)*w**2 - 10395.0_8/TWO) * cos(5.0_8*phi)
! l = 7, m = 6
rn(14) = 2.42182459624969_8 * w*(w2m1)**3 * cos(6.0_8*phi)
! l = 7, m = 7
rn(15) = 0.647259849287749_8 * (w2m1)**(7.0_8/TWO) * cos(7.0_8*phi)
case (8)
! l = 8, m = -8
rn(1) = 0.626706654240044_8 * (w2m1)**4 * sin(8.0_8*phi)
! l = 8, m = -7
rn(2) = 2.50682661696018_8 * w*(w2m1)**(7.0_8/TWO) * sin(7.0_8*phi)
! l = 8, m = -6
rn(3) = 6.77369783729086d-6*(w2m1)**3* &
((2027025.0_8/TWO)*w**2 - 135135.0_8/TWO) * sin(6.0_8*phi)
! l = 8, m = -5
rn(4) = 4.38985792528482d-5*(w2m1)**(5.0_8/TWO)* &
((675675.0_8/TWO)*w**3 - 135135.0_8/TWO*w) * sin(5.0_8*phi)
! l = 8, m = -4
rn(5) = 0.000316557156832328_8 * (w2m1)**2* &
((675675.0_8/8.0_8)*w**4 - 135135.0_8/4.0_8 * w**2 + 10395.0_8/8.0_8) * sin(4.0_8*phi)
! l = 8, m = -3
rn(6) = 0.00245204119306875_8 * (w2m1)**(3.0_8/TWO)* &
((135135.0_8/8.0_8)*w**5 - 45045.0_8/4.0_8 * w**3 + (10395.0_8/8.0_8)*w) * sin(3.0_8*phi)
! l = 8, m = -2
rn(7) = 0.0199204768222399_8 * (w2m1)* &
((45045.0_8/16.0_8)*w**6- 45045.0_8/16.0_8 * w**4 + &
(10395.0_8/16.0_8)*w**2 - 315.0_8/16.0_8) * sin(TWO*phi)
! l = 8, m = -1
rn(8) = 0.166666666666667_8*sqrt(w2m1)* &
((6435.0_8/16.0_8)*w**7 - 9009.0_8/16.0_8 * w**5 + &
(3465.0_8/16.0_8)*w**3 - 315.0_8/16.0_8 * w) * sin(phi)
! l = 8, m = 0
rn(9) = 50.2734375_8 * w**8 - 93.84375_8 * w**6 + 54.140625_8 * w**4 -&
9.84375_8 * w**2 + 0.2734375_8
! l = 8, m = 1
rn(10) = 0.166666666666667_8*sqrt(w2m1)* &
((6435.0_8/16.0_8)*w**7 - 9009.0_8/16.0_8 * w**5 + &
(3465.0_8/16.0_8)*w**3 - 315.0_8/16.0_8 * w) * cos(phi)
! l = 8, m = 2
rn(11) = 0.0199204768222399_8 * (w2m1)*((45045.0_8/16.0_8)*w**6- &
45045.0_8/16.0_8 * w**4 + (10395.0_8/16.0_8)*w**2 - &
315.0_8/16.0_8) * cos(TWO*phi)
! l = 8, m = 3
rn(12) = 0.00245204119306875_8 * (w2m1)**(3.0_8/TWO)* &
((135135.0_8/8.0_8)*w**5 - 45045.0_8/4.0_8 * w**3 + &
(10395.0_8/8.0_8)*w) * cos(3.0_8*phi)
! l = 8, m = 4
rn(13) = 0.000316557156832328_8 * (w2m1)**2*((675675.0_8/8.0_8)*w**4 - &
135135.0_8/4.0_8 * w**2 + 10395.0_8/8.0_8) * cos(4.0_8*phi)
! l = 8, m = 5
rn(14) = 4.38985792528482d-5*(w2m1)**(5.0_8/TWO)*((675675.0_8/TWO)*w**3 - &
135135.0_8/TWO*w) * cos(5.0_8*phi)
! l = 8, m = 6
rn(15) = 6.77369783729086d-6*(w2m1)**3*((2027025.0_8/TWO)*w**2 - &
135135.0_8/TWO) * cos(6.0_8*phi)
! l = 8, m = 7
rn(16) = 2.50682661696018_8 * w*(w2m1)**(7.0_8/TWO) * cos(7.0_8*phi)
! l = 8, m = 8
rn(17) = 0.626706654240044_8 * (w2m1)**4 * cos(8.0_8*phi)
case (9)
! l = 9, m = -9
rn(1) = 0.609049392175524_8 * (w2m1)**(9.0_8/TWO) * sin(9.0_8*phi)
! l = 9, m = -8
rn(2) = 2.58397773170915_8 * w*(w2m1)**4 * sin(8.0_8*phi)
! l = 9, m = -7
rn(3) = 4.37240315267812d-7*(w2m1)**(7.0_8/TWO)* &
((34459425.0_8/TWO)*w**2 - 2027025.0_8/TWO) * sin(7.0_8*phi)
! l = 9, m = -6
rn(4) = 3.02928976464514d-6*(w2m1)**3* &
((11486475.0_8/TWO)*w**3 - 2027025.0_8/TWO*w) * sin(6.0_8*phi)
! l = 9, m = -5
rn(5) = 2.34647776186144d-5*(w2m1)**(5.0_8/TWO)* &
((11486475.0_8/8.0_8)*w**4 - 2027025.0_8/4.0_8 * w**2 + &
135135.0_8/8.0_8) * sin(5.0_8*phi)
! l = 9, m = -4
rn(6) = 0.000196320414650061_8 * (w2m1)**2*((2297295.0_8/8.0_8)*w**5 - &
675675.0_8/4.0_8 * w**3 + (135135.0_8/8.0_8)*w) * sin(4.0_8*phi)
! l = 9, m = -3
rn(7) = 0.00173385495536766_8 * (w2m1)**(3.0_8/TWO)* &
((765765.0_8/16.0_8)*w**6 - 675675.0_8/16.0_8 * w**4 + &
(135135.0_8/16.0_8)*w**2 - 3465.0_8/16.0_8) * sin(3.0_8*phi)
! l = 9, m = -2
rn(8) = 0.0158910431540932_8 * (w2m1)*((109395.0_8/16.0_8)*w**7- &
135135.0_8/16.0_8 * w**5 + (45045.0_8/16.0_8)*w**3 - 3465.0_8/16.0_8 * w)* &
sin(TWO*phi)
! l = 9, m = -1
rn(9) = 0.149071198499986_8*sqrt(w2m1)*((109395.0_8/128.0_8)*w**8 - &
45045.0_8/32.0_8 * w**6 + (45045.0_8/64.0_8)*w**4 - 3465.0_8/32.0_8 * w**2 + 315.0_8/128.0_8) * sin(phi)
! l = 9, m = 0
rn(10) = 94.9609375_8 * w**9 - 201.09375_8 * w**7 + 140.765625_8 * w**5- &
36.09375_8 * w**3 + 2.4609375_8 * w
! l = 9, m = 1
rn(11) = 0.149071198499986_8*sqrt(w2m1)*((109395.0_8/128.0_8)*w**8 - &
45045.0_8/32.0_8 * w**6 + (45045.0_8/64.0_8)*w**4 -3465.0_8/32.0_8 * w**2 + 315.0_8/128.0_8) * cos(phi)
! l = 9, m = 2
rn(12) = 0.0158910431540932_8 * (w2m1)*((109395.0_8/16.0_8)*w**7 - &
135135.0_8/16.0_8 * w**5 + (45045.0_8/16.0_8)*w**3 - 3465.0_8/ 16.0_8 * w) * &
cos(TWO*phi)
! l = 9, m = 3
rn(13) = 0.00173385495536766_8 * (w2m1)**(3.0_8/TWO)*((765765.0_8/16.0_8)*w**6 - &
675675.0_8/16.0_8 * w**4 + (135135.0_8/16.0_8)*w**2 - 3465.0_8/16.0_8)* &
cos(3.0_8*phi)
! l = 9, m = 4
rn(14) = 0.000196320414650061_8 * (w2m1)**2*((2297295.0_8/8.0_8)*w**5 - &
675675.0_8/4.0_8 * w**3 + (135135.0_8/8.0_8)*w) * cos(4.0_8*phi)
! l = 9, m = 5
rn(15) = 2.34647776186144d-5*(w2m1)**(5.0_8/TWO)*((11486475.0_8/8.0_8)* &
w**4 - 2027025.0_8/4.0_8 * w**2 + 135135.0_8/8.0_8) * cos(5.0_8*phi)
! l = 9, m = 6
rn(16) = 3.02928976464514d-6*(w2m1)**3*((11486475.0_8/TWO)*w**3 - &
2027025.0_8/TWO*w) * cos(6.0_8*phi)
! l = 9, m = 7
rn(17) = 4.37240315267812d-7*(w2m1)**(7.0_8/TWO)* &
((34459425.0_8/TWO)*w**2 - 2027025.0_8/TWO) * cos(7.0_8*phi)
! l = 9, m = 8
rn(18) = 2.58397773170915_8 * w*(w2m1)**4 * cos(8.0_8*phi)
! l = 9, m = 9
rn(19) = 0.609049392175524_8 * (w2m1)**(9.0_8/TWO) * cos(9.0_8*phi)
case (10)
! l = 10, m = -10
rn(1) = 0.593627917136573_8 * (w2m1)**5 * sin(10.0_8*phi)
! l = 10, m = -9
rn(2) = 2.65478475211798_8 * w*(w2m1)**(9.0_8/TWO) * sin(9.0_8*phi)
! l = 10, m = -8
rn(3) = 2.49953651452314d-8*(w2m1)**4*((654729075.0_8/TWO)*w**2 - &
34459425.0_8/TWO) * sin(8.0_8*phi)
! l = 10, m = -7
rn(4) = 1.83677671621093d-7*(w2m1)**(7.0_8/TWO)* &
((218243025.0_8/TWO)*w**3 - 34459425.0_8/TWO*w) * sin(7.0_8*phi)
! l = 10, m = -6
rn(5) = 1.51464488232257d-6*(w2m1)**3*((218243025.0_8/8.0_8)*w**4 - &
34459425.0_8/4.0_8 * w**2 + 2027025.0_8/8.0_8) * sin(6.0_8*phi)
! l = 10, m = -5
rn(6) = 1.35473956745817d-5*(w2m1)**(5.0_8/TWO)* &
((43648605.0_8/8.0_8)*w**5 - 11486475.0_8/4.0_8 * w**3 + &
(2027025.0_8/8.0_8)*w) * sin(5.0_8*phi)
! l = 10, m = -4
rn(7) = 0.000128521880085575_8 * (w2m1)**2*((14549535.0_8/16.0_8)*w**6 - &
11486475.0_8/16.0_8 * w**4 + (2027025.0_8/16.0_8)*w**2 - &
45045.0_8/16.0_8) * sin(4.0_8*phi)
! l = 10, m = -3
rn(8) = 0.00127230170115096_8 * (w2m1)**(3.0_8/TWO)* &
((2078505.0_8/16.0_8)*w**7 - 2297295.0_8/16.0_8 * w**5 + &
(675675.0_8/16.0_8)*w**3 - 45045.0_8/16.0_8 * w) * sin(3.0_8*phi)
! l = 10, m = -2
rn(9) = 0.012974982402692_8 * (w2m1)*((2078505.0_8/128.0_8)*w**8 - &
765765.0_8/32.0_8 * w**6 + (675675.0_8/64.0_8)*w**4 - &
45045.0_8/32.0_8 * w**2 + 3465.0_8/128.0_8) * sin(TWO*phi)
! l = 10, m = -1
rn(10) = 0.134839972492648_8*sqrt(w2m1)*((230945.0_8/128.0_8)*w**9 - &
109395.0_8/32.0_8 * w**7 + (135135.0_8/64.0_8)*w**5 - &
15015.0_8/32.0_8 * w**3 + (3465.0_8/128.0_8)*w) * sin(phi)
! l = 10, m = 0
rn(11) = 180.42578125_8 * w**10 - 427.32421875_8 * w**8 +351.9140625_8 * w**6 - &
117.3046875_8 * w**4 + 13.53515625_8 * w**2 -0.24609375_8
! l = 10, m = 1
rn(12) = 0.134839972492648_8*sqrt(w2m1)*((230945.0_8/128.0_8)*w**9 - &
109395.0_8/32.0_8 * w**7 + (135135.0_8/64.0_8)*w**5 -15015.0_8/ &
32.0_8 * w**3 + (3465.0_8/128.0_8)*w) * cos(phi)
! l = 10, m = 2
rn(13) = 0.012974982402692_8 * (w2m1)*((2078505.0_8/128.0_8)*w**8 - &
765765.0_8/32.0_8 * w**6 + (675675.0_8/64.0_8)*w**4 -&
45045.0_8/32.0_8 * w**2 + 3465.0_8/128.0_8) * cos(TWO*phi)
! l = 10, m = 3
rn(14) = 0.00127230170115096_8 * (w2m1)**(3.0_8/TWO)* &
((2078505.0_8/16.0_8)*w**7 - 2297295.0_8/16.0_8 * w**5 + &
(675675.0_8/16.0_8)*w**3 - 45045.0_8/16.0_8 * w) * cos(3.0_8*phi)
! l = 10, m = 4
rn(15) = 0.000128521880085575_8 * (w2m1)**2*((14549535.0_8/16.0_8)*w**6 - &
11486475.0_8/16.0_8 * w**4 + (2027025.0_8/16.0_8)*w**2 - &
45045.0_8/16.0_8) * cos(4.0_8*phi)
! l = 10, m = 5
rn(16) = 1.35473956745817d-5*(w2m1)**(5.0_8/TWO)* &
((43648605.0_8/8.0_8)*w**5 - 11486475.0_8/4.0_8 * w**3 + &
(2027025.0_8/8.0_8)*w) * cos(5.0_8*phi)
! l = 10, m = 6
rn(17) = 1.51464488232257d-6*(w2m1)**3*((218243025.0_8/8.0_8)*w**4 - &
34459425.0_8/4.0_8 * w**2 + 2027025.0_8/8.0_8) * cos(6.0_8*phi)
! l = 10, m = 7
rn(18) = 1.83677671621093d-7*(w2m1)**(7.0_8/TWO)* &
((218243025.0_8/TWO)*w**3 - 34459425.0_8/TWO*w) * cos(7.0_8*phi)
! l = 10, m = 8
rn(19) = 2.49953651452314d-8*(w2m1)**4* &
((654729075.0_8/TWO)*w**2 - 34459425.0_8/TWO) * cos(8.0_8*phi)
! l = 10, m = 9
rn(20) = 2.65478475211798_8 * w*(w2m1)**(9.0_8/TWO) * cos(9.0_8*phi)
! l = 10, m = 10
rn(21) = 0.593627917136573_8 * (w2m1)**5 * cos(10.0_8*phi)
case default
rn = ONE
end select
end function calc_rn
!===============================================================================
! MAXWELL_SPECTRUM samples an energy from the Maxwell fission distribution based
! on a direct sampling scheme. The probability distribution function for a

114
src/output.F90
View file

@ -672,7 +672,7 @@ contains
integer :: j ! index in filters array
integer :: id ! user-specified id
integer :: unit_ ! unit to write to
integer :: n ! scattering order to include in name
integer :: n ! moment order to include in name
character(MAX_LINE_LEN) :: string
character(MAX_WORD_LEN) :: pn_string
type(Cell), pointer :: c => null()
@ -825,20 +825,63 @@ contains
select case (t % score_bins(j))
case (SCORE_FLUX)
string = trim(string) // ' flux'
case (SCORE_FLUX_YN)
pn_string = ' flux'
string = trim(string) // pn_string
do n = 1, t % moment_order(j)
pn_string = ' flux-y' // trim(to_str(n))
string = trim(string) // pn_string
end do
j = j + n - 1
case (SCORE_TOTAL)
string = trim(string) // ' total'
case (SCORE_TOTAL_YN)
pn_string = ' total'
string = trim(string) // pn_string
do n = 1, t % moment_order(j)
pn_string = ' total-y' // trim(to_str(n))
string = trim(string) // pn_string
end do
j = j + n - 1
case (SCORE_SCATTER)
string = trim(string) // ' scatter'
case (SCORE_NU_SCATTER)
string = trim(string) // ' nu-scatter'
case (SCORE_SCATTER_N)
pn_string = ' scatter-' // trim(to_str(t % scatt_order(j)))
pn_string = ' scatter-' // trim(to_str(t % moment_order(j)))
string = trim(string) // pn_string
case (SCORE_SCATTER_PN)
pn_string = ' scatter'
string = trim(string) // pn_string
do n = 1, t % scatt_order(j)
pn_string = ' scatter-' // trim(to_str(n))
do n = 1, t % moment_order(j)
pn_string = ' scatter-p' // trim(to_str(n))
string = trim(string) // pn_string
end do
j = j + n - 1
case (SCORE_NU_SCATTER_N)
pn_string = ' nu-scatter-' // trim(to_str(t % moment_order(j)))
string = trim(string) // pn_string
case (SCORE_NU_SCATTER_PN)
pn_string = ' nu-scatter'
string = trim(string) // pn_string
do n = 1, t % moment_order(j)
pn_string = ' nu-scatter-p' // trim(to_str(n))
string = trim(string) // pn_string
end do
j = j + n - 1
case (SCORE_SCATTER_YN)
pn_string = ' scatter'
string = trim(string) // pn_string
do n = 1, t % moment_order(j)
pn_string = ' scatter-y' // trim(to_str(n))
string = trim(string) // pn_string
end do
j = j + n - 1
case (SCORE_NU_SCATTER_YN)
pn_string = ' nu-scatter'
string = trim(string) // pn_string
do n = 1, t % moment_order(j)
pn_string = ' nu-scatter-y' // trim(to_str(n))
string = trim(string) // pn_string
end do
j = j + n - 1
@ -1614,13 +1657,14 @@ contains
integer :: score_index ! scoring bin index
integer :: i_nuclide ! index in nuclides array
integer :: i_listing ! index in xs_listings array
integer :: n_order ! loop index for scattering orders
integer :: n_order ! loop index for moment orders
integer :: nm_order ! loop index for Ynm moment orders
real(8) :: t_value ! t-values for confidence intervals
real(8) :: alpha ! significance level for CI
character(MAX_FILE_LEN) :: filename ! name of output file
character(15) :: filter_name(N_FILTER_TYPES) ! names of tally filters
character(27) :: score_names(N_SCORE_TYPES) ! names of scoring function
character(27) :: score_name ! names of scoring function
character(36) :: score_names(N_SCORE_TYPES) ! names of scoring function
character(36) :: score_name ! names of scoring function
! to be applied at write-time
type(TallyObject), pointer :: t
@ -1642,8 +1686,6 @@ contains
score_names(abs(SCORE_TOTAL)) = "Total Reaction Rate"
score_names(abs(SCORE_SCATTER)) = "Scattering Rate"
score_names(abs(SCORE_NU_SCATTER)) = "Scattering Production Rate"
score_names(abs(SCORE_SCATTER_N)) = ""
score_names(abs(SCORE_SCATTER_PN)) = ""
score_names(abs(SCORE_TRANSPORT)) = "Transport Rate"
score_names(abs(SCORE_N_1N)) = "(n,1n) Rate"
score_names(abs(SCORE_ABSORPTION)) = "Absorption Rate"
@ -1651,6 +1693,14 @@ contains
score_names(abs(SCORE_NU_FISSION)) = "Nu-Fission Rate"
score_names(abs(SCORE_KAPPA_FISSION)) = "Kappa-Fission Rate"
score_names(abs(SCORE_EVENTS)) = "Events"
score_names(abs(SCORE_FLUX_YN)) = "Flux Moment"
score_names(abs(SCORE_TOTAL_YN)) = "Total Reaction Rate Moment"
score_names(abs(SCORE_SCATTER_N)) = "Scattering Rate Moment"
score_names(abs(SCORE_SCATTER_PN)) = "Scattering Rate Moment"
score_names(abs(SCORE_SCATTER_YN)) = "Scattering Rate Moment"
score_names(abs(SCORE_NU_SCATTER_N)) = "Scattering Prod. Rate Moment"
score_names(abs(SCORE_NU_SCATTER_PN)) = "Scattering Prod. Rate Moment"
score_names(abs(SCORE_NU_SCATTER_YN)) = "Scattering Prod. Rate Moment"
! Create filename for tally output
filename = trim(path_output) // "tallies.out"
@ -1777,34 +1827,42 @@ contains
do l = 1, t % n_user_score_bins
k = k + 1
score_index = score_index + 1
if (t % score_bins(k) == SCORE_SCATTER_N) then
if (t % scatt_order(k) == 0) then
score_name = "Scattering Rate"
else
score_name = 'P' // trim(to_str(t % scatt_order(k))) // &
' Scattering Moment'
end if
select case(t % score_bins(k))
case (SCORE_SCATTER_N, SCORE_NU_SCATTER_N)
score_name = 'P' // trim(to_str(t % moment_order(k))) // " " // &
score_names(abs(t % score_bins(k)))
write(UNIT=UNIT_TALLY, FMT='(1X,2A,1X,A,"+/- ",A)') &
repeat(" ", indent), score_name, &
to_str(t % results(score_index,filter_index) % sum), &
trim(to_str(t % results(score_index,filter_index) % sum_sq))
else if (t % score_bins(k) == SCORE_SCATTER_PN) then
score_name = "Scattering Rate"
write(UNIT=UNIT_TALLY, FMT='(1X,2A,1X,A,"+/- ",A)') &
repeat(" ", indent), score_name, &
to_str(t % results(score_index,filter_index) % sum), &
trim(to_str(t % results(score_index,filter_index) % sum_sq))
do n_order = 1, t % scatt_order(k)
case (SCORE_SCATTER_PN, SCORE_NU_SCATTER_PN)
score_index = score_index - 1
do n_order = 0, t % moment_order(k)
score_index = score_index + 1
score_name = 'P' // trim(to_str(n_order)) // &
' Scattering Moment'
score_name = 'P' // trim(to_str(n_order)) // " " //&
score_names(abs(t % score_bins(k)))
write(UNIT=UNIT_TALLY, FMT='(1X,2A,1X,A,"+/- ",A)') &
repeat(" ", indent), score_name, &
to_str(t % results(score_index,filter_index) % sum), &
trim(to_str(t % results(score_index,filter_index) % sum_sq))
end do
k = k + n_order - 1
else
k = k + t % moment_order(k)
case (SCORE_SCATTER_YN, SCORE_NU_SCATTER_YN, SCORE_FLUX_YN, &
SCORE_TOTAL_YN)
score_index = score_index - 1
do n_order = 0, t % moment_order(k)
do nm_order = -n_order, n_order
score_index = score_index + 1
score_name = 'Y' // trim(to_str(n_order)) // ',' // &
trim(to_str(nm_order)) // " " // score_names(abs(t % score_bins(k)))
write(UNIT=UNIT_TALLY, FMT='(1X,2A,1X,A,"+/- ",A)') &
repeat(" ", indent), score_name, &
to_str(t % results(score_index,filter_index) % sum), &
trim(to_str(t % results(score_index,filter_index) % sum_sq))
end do
end do
k = k + (t % moment_order(k) + 1)**2 - 1
case default
if (t % score_bins(k) > 0) then
score_name = reaction_name(t % score_bins(k))
else
@ -1814,7 +1872,7 @@ contains
repeat(" ", indent), score_name, &
to_str(t % results(score_index,filter_index) % sum), &
trim(to_str(t % results(score_index,filter_index) % sum_sq))
end if
end select
end do
indent = indent - 2

5
src/particle_header.F90
View file

@ -30,7 +30,7 @@ module particle_header
! Pointer to next (more local) set of coordinates
type(LocalCoord), pointer :: next => null()
end type LocalCoord
!===============================================================================
! PARTICLE describes the state of a particle being transported through the
! geometry
@ -53,6 +53,7 @@ module particle_header
! Pre-collision physical data
real(8) :: last_xyz(3) ! previous coordinates
real(8) :: last_uvw(3) ! previous direction coordinates
real(8) :: last_wgt ! pre-collision particle weight
real(8) :: last_E ! pre-collision energy
real(8) :: absorb_wgt ! weight absorbed for survival biasing
@ -96,7 +97,7 @@ contains
type(LocalCoord), pointer :: coord
if (associated(coord)) then
if (associated(coord)) then
! recursively deallocate lower coordinates
if (associated(coord % next)) call deallocate_coord(coord%next)

3
src/particle_restart.F90
View file

@ -1,4 +1,4 @@
module particle_restart
module particle_restart
use, intrinsic :: ISO_FORTRAN_ENV
@ -88,6 +88,7 @@ contains
! Set particle last attributes
p % last_wgt = p % wgt
p % last_xyz = p % coord % xyz
p % last_uvw = p % coord % uvw
p % last_E = p % E
! Close hdf5 file

1
src/physics.F90
View file

@ -36,6 +36,7 @@ contains
! Store pre-collision particle properties
p % last_wgt = p % wgt
p % last_E = p % E
p % last_uvw = p % coord0 % uvw
! Add to collision counter for particle
p % n_collision = p % n_collision + 1

1
src/source.F90
View file

@ -256,6 +256,7 @@ contains
p % coord % xyz = src % xyz
p % coord % uvw = src % uvw
p % last_xyz = src % xyz
p % last_uvw = src % uvw
p % E = src % E
p % last_E = src % E

24
src/state_point.F90
View file

@ -58,7 +58,7 @@ contains
call write_message(1)
if (master) then
! Create statepoint file
! Create statepoint file
call sp % file_create(filename)
! Write file type
@ -216,12 +216,12 @@ contains
group="tallies/tally" // to_str(i), length=t % n_nuclide_bins)
deallocate(temp_array)
! Write number of score bins, score bins, and scatt order
! Write number of score bins, score bins, and moment order
call sp % write_data(t % n_score_bins, "n_score_bins", &
group="tallies/tally" // to_str(i))
call sp % write_data(t % score_bins, "score_bins", &
group="tallies/tally" // to_str(i), length=t % n_score_bins)
call sp % write_data(t % scatt_order, "scatt_order", &
call sp % write_data(t % moment_order, "moment_order", &
group="tallies/tally" // to_str(i), length=t % n_score_bins)
! Write number of user score bins
@ -409,7 +409,7 @@ contains
! Copy global tallies into temporary array for reducing
n_bins = 2 * N_GLOBAL_TALLIES
global_temp(1,:) = global_tallies(:) % sum
global_temp(2,:) = global_tallies(:) % sum_sq
global_temp(2,:) = global_tallies(:) % sum_sq
if (master) then
! The MPI_IN_PLACE specifier allows the master to copy values into a
@ -430,7 +430,7 @@ contains
tallyresult_temp(:,1) % sum = global_temp(1,:)
tallyresult_temp(:,1) % sum_sq = global_temp(2,:)
! Write out global tallies sum and sum_sq
call sp % write_tally_result(tallyresult_temp, "global_tallies", &
n1=N_GLOBAL_TALLIES, n2=1)
@ -484,7 +484,7 @@ contains
allocate(tallyresult_temp(m,n))
tallyresult_temp(:,:) % sum = tally_temp(1,:,:)
tallyresult_temp(:,:) % sum_sq = tally_temp(2,:,:)
! Write reduced tally results to file
call sp % write_tally_result(t % results, "results", &
group="tallies/tally" // to_str(i), n1=m, n2=n)
@ -525,7 +525,7 @@ contains
integer :: int_array(3)
integer, allocatable :: temp_array(:)
logical :: source_present
real(8) :: real_array(3)
real(8) :: real_array(3)
type(TallyObject), pointer :: t => null()
! Write message
@ -720,7 +720,7 @@ contains
group="tallies/tally" // to_str(i))
call sp % read_data(t % score_bins, "score_bins", &
group="tallies/tally" // to_str(i), length=t % n_score_bins)
call sp % read_data(t % scatt_order, "scatt_order", &
call sp % read_data(t % moment_order, "moment_order", &
group="tallies/tally" // to_str(i), length=t % n_score_bins)
! Write number of user score bins
@ -741,7 +741,7 @@ contains
if (path_source_point == path_state_point .and. .not. source_present) then
message = "Source bank must be contained in statepoint restart file"
call fatal_error()
end if
end if
! Read tallies to master
if (master) then
@ -779,20 +779,20 @@ contains
end if
end if
! Read source if in eigenvalue mode
! Read source if in eigenvalue mode
if (run_mode == MODE_EIGENVALUE) then
! Check if source was written out separately
if (.not. source_present) then
! Close statepoint file
! Close statepoint file
call sp % file_close()
! Write message
message = "Loading source file " // trim(path_source_point) // "..."
call write_message(1)
! Open source file
! Open source file
call sp % file_open(path_source_point, 'r', serial = .false.)
! Read file type

550
src/tally.F90
View file

@ -41,7 +41,8 @@ contains
integer :: i_tally
integer :: j ! loop index for scoring bins
integer :: k ! loop index for nuclide bins
integer :: n ! loop index for scattering order
integer :: n ! loop index for legendre order
integer :: num_nm ! Number of N,M orders in harmonic
integer :: l ! scoring bin loop index, allowing for changing
! position during the loop
integer :: filter_index ! single index for single bin
@ -148,6 +149,42 @@ contains
end if
score = score / material_xs % total
case (SCORE_FLUX_YN)
! All events score to a flux bin. We actually use a collision
! estimator since there is no way to count 'events' exactly for
! the flux
score_index = score_index - 1
! get the score
if (survival_biasing) then
! We need to account for the fact that some weight was already
! absorbed
score = last_wgt + p % absorb_wgt
else
score = last_wgt
end if
score = score / material_xs % total
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % last_uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TOTAL)
! All events will score to the total reaction rate. We can just
@ -162,6 +199,41 @@ contains
score = last_wgt
end if
case (SCORE_TOTAL_YN)
! All events will score to the total reaction rate. We can just
! use the weight of the particle entering the collision as the
! score
score_index = score_index - 1
! get the score
if (survival_biasing) then
! We need to account for the fact that some weight was already
! absorbed
score = last_wgt + p % absorb_wgt
else
score = last_wgt
end if
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % last_uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_SCATTER)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
@ -172,7 +244,7 @@ contains
score = last_wgt
case (SCORE_NU_SCATTER)
case (SCORE_NU_SCATTER)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
@ -181,7 +253,7 @@ contains
! reaction with neutrons in the exit channel
score = wgt
case (SCORE_SCATTER_N)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
@ -189,33 +261,129 @@ contains
! Find the scattering order for a singly requested moment, and
! store its moment contribution.
if (t % scatt_order(j) == 1) then
if (t % moment_order(j) == 1) then
score = last_wgt * mu ! avoid function call overhead
else
score = last_wgt * calc_pn(t % scatt_order(j), mu)
score = last_wgt * calc_pn(t % moment_order(j), mu)
endif
case (SCORE_SCATTER_PN)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) then
j = j + t % scatt_order(j)
j = j + t % moment_order(j)
cycle SCORE_LOOP
end if
score_index = score_index - 1
! Find the scattering order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % scatt_order(j)
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + 1
! get the score and tally it
score = last_wgt * calc_pn(n, mu)
!$omp critical
t % results(score_index, filter_index) % value = &
t % results(score_index, filter_index) % value + score
!$omp end critical
end do
j = j + t % moment_order(j)
cycle SCORE_LOOP
case (SCORE_SCATTER_YN)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) then
j = j + t % moment_order(j)
cycle SCORE_LOOP
end if
score_index = score_index - 1
! Calculate the number of moments from t % moment_order
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! get the score of the scattering moment
score = last_wgt * calc_pn(n, mu)
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % last_uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_NU_SCATTER_N)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
! Find the scattering order for a singly requested moment, and
! store its moment contribution.
if (t % moment_order(j) == 1) then
score = wgt * mu ! avoid function call overhead
else
score = wgt * calc_pn(t % moment_order(j), mu)
endif
case (SCORE_NU_SCATTER_PN)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) then
j = j + t % moment_order(j)
cycle SCORE_LOOP
end if
score_index = score_index - 1
! Find the scattering order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + 1
! get the score and tally it
score = wgt * calc_pn(n, mu)
!$omp critical
t % results(score_index, filter_index) % value = &
t % results(score_index, filter_index) % value + score
!$omp end critical
end do
j = j + t % scatt_order(j)
j = j + t % moment_order(j)
cycle SCORE_LOOP
case (SCORE_NU_SCATTER_YN)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) then
j = j + t % moment_order(j)
cycle SCORE_LOOP
end if
score_index = score_index - 1
! Calculate the number of moments from t % moment_order
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! get the score of the scattering moment
score = wgt * calc_pn(n, mu)
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % last_uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TRANSPORT)
@ -335,12 +503,12 @@ contains
end if
end if
case (SCORE_KAPPA_FISSION)
if (survival_biasing) then
! No fission events occur if survival biasing is on -- need to
! calculate fraction of absorptions that would have resulted in
! fission and multiply by Q
! fission scale by kappa-fission
if (micro_xs(p % event_nuclide) % absorption > ZERO) then
score = p % absorb_wgt * &
@ -479,6 +647,9 @@ contains
integer :: k ! loop index for nuclide bins
integer :: l ! loop index for nuclides in material
integer :: m ! loop index for reactions
integer :: n ! loop index for legendre order
integer :: num_nm ! Number of N,M orders in harmonic
integer :: q ! loop index for scoring bins
integer :: filter_index ! single index for single bin
integer :: i_nuclide ! index in nuclides array (from bins)
integer :: i_nuc ! index in nuclides array (from material)
@ -565,10 +736,15 @@ contains
end if
! Determine score for each bin
SCORE_LOOP: do j = 1, t % n_score_bins
j = 0
SCORE_LOOP: do q = 1, t % n_user_score_bins
j = j + 1
! determine what type of score bin
score_bin = t % score_bins(j)
! determine scoring bin index
score_index = (k - 1)*t % n_score_bins + j
if (i_nuclide > 0) then
! ================================================================
! DETERMINE NUCLIDE CROSS SECTION
@ -578,11 +754,58 @@ contains
! For flux, we need no cross section
score = flux
case (SCORE_FLUX_YN)
score_index = score_index - 1
! For flux, we need no cross section
score = flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TOTAL)
! Total cross section is pre-calculated
score = micro_xs(i_nuclide) % total * &
atom_density * flux
case (SCORE_TOTAL_YN)
score_index = score_index - 1
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_SCATTER)
! Scattering cross section is pre-calculated
score = (micro_xs(i_nuclide) % total - &
@ -662,10 +885,60 @@ contains
! For flux, we need no cross section
score = flux
case (SCORE_FLUX_YN)
score_index = score_index - 1
! For flux, we need no cross section
score = flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TOTAL)
! Total cross section is pre-calculated
score = material_xs % total * flux
case (SCORE_TOTAL_YN)
score_index = score_index - 1
! Total cross section is pre-calculated
score = material_xs % total * flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_SCATTER)
! Scattering cross section is pre-calculated
score = (material_xs % total - material_xs % absorption) * flux
@ -704,7 +977,7 @@ contains
do l = 1, mat % n_nuclides
! Get atom density
atom_density = mat % atom_density(l)
! Get index in nuclides array
i_nuc = mat % nuclide(l)
@ -742,9 +1015,6 @@ contains
end select
end if
! Determine scoring bin index
score_index = (k - 1)*t % n_score_bins + j
! Add score to tally
!$omp critical
t % results(score_index, filter_index) % value = &
@ -785,6 +1055,9 @@ contains
integer :: i ! loop index for nuclides in material
integer :: j ! loop index for scoring bin types
integer :: m ! loop index for reactions in nuclide
integer :: n ! loop index for legendre order
integer :: num_nm ! Number of N,M orders in harmonic
integer :: q ! loop index for scoring bins
integer :: i_nuclide ! index in nuclides array
integer :: score_bin ! type of score, e.g. SCORE_FLUX
integer :: score_index ! scoring bin index
@ -815,18 +1088,73 @@ contains
atom_density = mat % atom_density(i)
! Loop over score types for each bin
SCORE_LOOP: do j = 1, t % n_score_bins
j = 0
SCORE_LOOP: do q = 1, t % n_user_score_bins
j = j + 1
! determine what type of score bin
score_bin = t % score_bins(j)
! Determine scoring bin index based on what the index of the nuclide
! is in the nuclides array
score_index = (i_nuclide - 1)*t % n_score_bins + j
! Determine macroscopic nuclide cross section
select case(score_bin)
case (SCORE_FLUX)
score = flux
case (SCORE_FLUX_YN)
score_index = score_index - 1
! For flux, we need no cross section
score = flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TOTAL)
score = micro_xs(i_nuclide) % total * atom_density * flux
case (SCORE_TOTAL_YN)
score_index = score_index - 1
score = micro_xs(i_nuclide) % total * atom_density * flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_SCATTER)
score = (micro_xs(i_nuclide) % total - &
micro_xs(i_nuclide) % absorption) * atom_density * flux
@ -851,7 +1179,7 @@ contains
! sections that are used often (e.g. n2n, ngamma, etc. for depletion),
! it might make sense to optimize this section or pre-calculate cross
! sections
if (score_bin > 1) then
! Set default score
score = ZERO
@ -886,10 +1214,6 @@ contains
end if
end select
! Determine scoring bin index based on what the index of the nuclide
! is in the nuclides array
score_index = (i_nuclide - 1)*t % n_score_bins + j
! Add score to tally
!$omp critical
t % results(score_index, filter_index) % value = &
@ -904,18 +1228,74 @@ contains
! SCORE TOTAL MATERIAL REACTION RATES
! Loop over score types for each bin
MATERIAL_SCORE_LOOP: do j = 1, t % n_score_bins
j = 0
MATERIAL_SCORE_LOOP: do q = 1, t % n_user_score_bins
j = j + 1
! determine what type of score bin
score_bin = t % score_bins(j)
! Determine scoring bin index based on what the index of the nuclide
! is in the nuclides array
score_index = n_nuclides_total*t % n_score_bins + j
! Determine macroscopic material cross section
select case(score_bin)
case (SCORE_FLUX)
score = flux
case (SCORE_FLUX_YN)
score_index = score_index - 1
! For flux, we need no cross section
score = flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle MATERIAL_SCORE_LOOP
case (SCORE_TOTAL)
score = material_xs % total * flux
case (SCORE_TOTAL_YN)
score_index = score_index - 1
! Total cross section is pre-calculated
score = material_xs % total * flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle MATERIAL_SCORE_LOOP
case (SCORE_SCATTER)
score = (material_xs % total - material_xs % absorption) * flux
@ -938,7 +1318,7 @@ contains
! Any other cross section has to be calculated on-the-fly. This is
! somewhat costly since it requires a loop over each nuclide in a
! material and each reaction in the nuclide
if (score_bin > 1) then
! Set default score
score = ZERO
@ -986,10 +1366,6 @@ contains
end if
end select
! Determine scoring bin index based on what the index of the nuclide
! is in the nuclides array
score_index = n_nuclides_total*t % n_score_bins + j
! Add score to tally
!$omp critical
t % results(score_index, filter_index) % value = &
@ -1016,6 +1392,9 @@ contains
integer :: j ! loop index for direction
integer :: k ! loop index for mesh cell crossings
integer :: b ! loop index for nuclide bins
integer :: n ! loop index for legendre order
integer :: num_nm ! Number of N,M orders in harmonic
integer :: q ! loop index for scoring bins
integer :: ijk0(3) ! indices of starting coordinates
integer :: ijk1(3) ! indices of ending coordinates
integer :: ijk_cross(3) ! indices of mesh cell crossed
@ -1241,18 +1620,75 @@ contains
end if
! Determine score for each bin
SCORE_LOOP: do j = 1, t % n_score_bins
j = 0
SCORE_LOOP: do q = 1, t % n_user_score_bins
j = j + 1
! determine what type of score bin
score_bin = t % score_bins(j)
! Determine scoring bin index
score_index = (b - 1)*t % n_score_bins + j
if (i_nuclide > 0) then
! Determine macroscopic nuclide cross section
! Determine macroscopic nuclide cross section
select case(score_bin)
case (SCORE_FLUX)
score = flux
case (SCORE_FLUX_YN)
score_index = score_index - 1
score = flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TOTAL)
score = micro_xs(i_nuclide) % total * &
atom_density * flux
case (SCORE_TOTAL_YN)
score_index = score_index - 1
! Total cross section is pre-calculated
score = micro_xs(i_nuclide) % total * &
atom_density * flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_SCATTER)
score = (micro_xs(i_nuclide) % total - &
micro_xs(i_nuclide) % absorption) * &
@ -1277,12 +1713,63 @@ contains
end select
else
! Determine macroscopic material cross section
! Determine macroscopic material cross section
select case(score_bin)
case (SCORE_FLUX)
score = flux
case (SCORE_FLUX_YN)
score_index = score_index - 1
score = flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_TOTAL)
score = material_xs % total * flux
case (SCORE_TOTAL_YN)
score_index = score_index - 1
! Total cross section is pre-calculated
score = material_xs % total * flux
num_nm = 1
! Find the order for a collection of requested moments
! and store the moment contribution of each
do n = 0, t % moment_order(j)
! determine scoring bin index
score_index = score_index + num_nm
! Update number of total n,m bins for this n (m = [-n: n])
num_nm = 2 * n + 1
! multiply score by the angular flux moments and store
!$omp critical
t % results(score_index: score_index + num_nm - 1, filter_index) % value = &
t % results(score_index: score_index + num_nm - 1, filter_index) % value + &
score * calc_rn(n, p % coord0 % uvw)
!$omp end critical
end do
j = j + (t % moment_order(j) + 1)**2 - 1
cycle SCORE_LOOP
case (SCORE_SCATTER)
score = (material_xs % total - material_xs % absorption) * flux
case (SCORE_ABSORPTION)
@ -1302,9 +1789,6 @@ contains
end select
end if
! Determine scoring bin index
score_index = (b - 1)*t % n_score_bins + j
! Add score to tally
!$omp critical
t % results(score_index, filter_index) % value = &

44
src/tally_header.F90
View file

@ -47,7 +47,7 @@ module tally_header
!===============================================================================
! TALLYFILTER describes a filter that limits what events score to a tally. For
! example, a cell filter indicates that only particles in a specified cell
! should score to the tally.
! should score to the tally.
!===============================================================================
type TallyFilter
@ -55,7 +55,7 @@ module tally_header
integer :: n_bins = 0
integer, allocatable :: int_bins(:)
real(8), allocatable :: real_bins(:) ! Only used for energy filters
! Type-Bound procedures
contains
procedure :: clear => tallyfilter_clear ! Deallocates TallyFilter
@ -105,7 +105,7 @@ module tally_header
! scattering response.
integer :: n_score_bins = 0
integer, allocatable :: score_bins(:)
integer, allocatable :: scatt_order(:)
integer, allocatable :: moment_order(:)
integer :: n_user_score_bins = 0
! Results for each bin -- the first dimension of the array is for scores
@ -122,14 +122,14 @@ module tally_header
! Number of realizations of tally random variables
integer :: n_realizations = 0
! Type-Bound procedures
contains
procedure :: clear => tallyobject_clear ! Deallocates TallyObject
end type TallyObject
contains
!===============================================================================
! TALLYFILTER_CLEAR deallocates a TallyFilter element and sets it to its as
! initialized state.
@ -137,16 +137,16 @@ module tally_header
subroutine tallyfilter_clear(this)
class(TallyFilter), intent(inout) :: this ! The TallyFilter to be cleared
this % type = NONE
this % n_bins = 0
if (allocated(this % int_bins)) &
deallocate(this % int_bins)
if (allocated(this % real_bins)) &
deallocate(this % real_bins)
end subroutine tallyfilter_clear
!===============================================================================
! TALLYOBJECT_CLEAR deallocates a TallyObject element and sets it to its as
! initialized state.
@ -154,44 +154,44 @@ module tally_header
subroutine tallyobject_clear(this)
class(TallyObject), intent(inout) :: this ! The TallyObject to be cleared
integer :: i ! Loop Index
! This routine will go through each item in TallyObject and set the value
! to its default, as-initialized values, including deallocations.
this % label = ""
if (allocated(this % filters)) then
do i = 1, size(this % filters)
call this % filters(i) % clear()
end do
deallocate(this % filters)
end if
if (allocated(this % stride)) &
deallocate(this % stride)
this % find_filter = 0
this % n_nuclide_bins = 0
if (allocated(this % nuclide_bins)) &
deallocate(this % nuclide_bins)
this % all_nuclides = .false.
this % n_score_bins = 0
if (allocated(this % score_bins)) &
deallocate(this % score_bins)
if (allocated(this % scatt_order)) &
deallocate(this % scatt_order)
if (allocated(this % moment_order)) &
deallocate(this % moment_order)
this % n_user_score_bins = 0
if (allocated(this % results)) &
deallocate(this % results)
this % reset = .false.
this % n_realizations = 0
end subroutine tallyobject_clear
end module tally_header

2
src/tracking.F90
View file

@ -66,7 +66,7 @@ contains
total_weight = total_weight + p % wgt
!$omp end critical
! Force calculation of cross-sections by setting last energy to zero
! Force calculation of cross-sections by setting last energy to zero
micro_xs % last_E = ZERO
! Prepare to write out particle track.

156
src/utils/statepoint.py
View file

@ -6,81 +6,89 @@ from collections import OrderedDict
import numpy as np
import scipy.stats
REVISION_STATEPOINT = 12
filter_types = {1: 'universe', 2: 'material', 3: 'cell', 4: 'cellborn',
5: 'surface', 6: 'mesh', 7: 'energyin', 8: 'energyout'}
score_types = {-1: 'flux',
-2: 'total',
-3: 'scatter',
-4: 'nu-scatter',
-5: 'scatter-n',
-6: 'scatter-pn',
-7: 'transport',
-8: 'n1n',
-9: 'absorption',
-10: 'fission',
-11: 'nu-fission',
-12: 'kappa-fission',
-13: 'current',
-14: 'events',
1: '(n,total)',
2: '(n,elastic)',
4: '(n,level)',
11: '(n,2nd)',
16: '(n,2n)',
17: '(n,3n)',
18: '(n,fission)',
19: '(n,f)',
20: '(n,nf)',
21: '(n,2nf)',
22: '(n,na)',
23: '(n,n3a)',
24: '(n,2na)',
25: '(n,3na)',
28: '(n,np)',
29: '(n,n2a)',
30: '(n,2n2a)',
32: '(n,nd)',
33: '(n,nt)',
34: '(n,nHe-3)',
35: '(n,nd2a)',
36: '(n,nt2a)',
37: '(n,4n)',
38: '(n,3nf)',
41: '(n,2np)',
42: '(n,3np)',
44: '(n,n2p)',
45: '(n,npa)',
91: '(n,nc)',
101: '(n,disappear)',
102: '(n,gamma)',
103: '(n,p)',
104: '(n,d)',
105: '(n,t)',
106: '(n,3He)',
107: '(n,a)',
108: '(n,2a)',
109: '(n,3a)',
111: '(n,2p)',
112: '(n,pa)',
113: '(n,t2a)',
114: '(n,d2a)',
115: '(n,pd)',
116: '(n,pt)',
117: '(n,da)',
201: '(n,Xn)',
202: '(n,Xgamma)',
203: '(n,Xp)',
204: '(n,Xd)',
205: '(n,Xt)',
206: '(n,X3He)',
207: '(n,Xa)',
444: '(damage)',
649: '(n,pc)',
699: '(n,dc)',
749: '(n,tc)',
799: '(n,3Hec)',
849: '(n,tc)'}
-2: 'total',
-3: 'scatter',
-4: 'nu-scatter',
-5: 'scatter-n',
-6: 'scatter-pn',
-7: 'nu-scatter-n',
-8: 'nu-scatter-pn',
-9: 'transport',
-10: 'n1n',
-11: 'absorption',
-12: 'fission',
-13: 'nu-fission',
-14: 'kappa-fission',
-15: 'current',
-16: 'flux-yn',
-17: 'total-yn',
-18: 'scatter-yn',
-19: 'nu-scatter-yn',
-20: 'events',
1: '(n,total)',
2: '(n,elastic)',
4: '(n,level)',
11: '(n,2nd)',
16: '(n,2n)',
17: '(n,3n)',
18: '(n,fission)',
19: '(n,f)',
20: '(n,nf)',
21: '(n,2nf)',
22: '(n,na)',
23: '(n,n3a)',
24: '(n,2na)',
25: '(n,3na)',
28: '(n,np)',
29: '(n,n2a)',
30: '(n,2n2a)',
32: '(n,nd)',
33: '(n,nt)',
34: '(n,nHe-3)',
35: '(n,nd2a)',
36: '(n,nt2a)',
37: '(n,4n)',
38: '(n,3nf)',
41: '(n,2np)',
42: '(n,3np)',
44: '(n,n2p)',
45: '(n,npa)',
91: '(n,nc)',
101: '(n,disappear)',
102: '(n,gamma)',
103: '(n,p)',
104: '(n,d)',
105: '(n,t)',
106: '(n,3He)',
107: '(n,a)',
108: '(n,2a)',
109: '(n,3a)',
111: '(n,2p)',
112: '(n,pa)',
113: '(n,t2a)',
114: '(n,d2a)',
115: '(n,pd)',
116: '(n,pt)',
117: '(n,da)',
201: '(n,Xn)',
202: '(n,Xgamma)',
203: '(n,Xp)',
204: '(n,Xd)',
205: '(n,Xt)',
206: '(n,X3He)',
207: '(n,Xa)',
444: '(damage)',
649: '(n,pc)',
699: '(n,dc)',
749: '(n,tc)',
799: '(n,3Hec)',
849: '(n,tc)'}
score_types.update({MT: '(n,n' + str(MT-50) + ')' for MT in range(51,91)})
score_types.update({MT: '(n,p' + str(MT-600) + ')' for MT in range(600,649)})
score_types.update({MT: '(n,d' + str(MT-650) + ')' for MT in range(650,699)})
@ -151,7 +159,7 @@ class StatePoint(object):
# Read statepoint revision
self.revision = self._get_int(path='revision')[0]
if self.revision != 11:
if self.revision != REVISION_STATEPOINT:
raise Exception('Statepoint Revision is not consistent.')
# Read OpenMC version
@ -287,7 +295,7 @@ class StatePoint(object):
t.n_scores = self._get_int(path=base+'n_score_bins')[0]
t.scores = [score_types[j] for j in self._get_int(
t.n_scores, path=base+'score_bins')]
t.scatt_order = self._get_int(t.n_scores, path=base+'scatt_order')
t.moment_order = self._get_int(t.n_scores, path=base+'moment_order')
# Read number of user score bins
t.n_user_scores = self._get_int(path=base+'n_user_score_bins')[0]
@ -301,7 +309,7 @@ class StatePoint(object):
# Source bank present
source_present = self._get_int(path='source_present')[0]
if source_present == 1:
self.source_present = True
self.source_present = True
else:
self.source_present = False

185
tests/test_score_flux_yn/geometry.xml Normal file
View file

@ -0,0 +1,185 @@
<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" surfaces=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" surfaces=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" surfaces=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" surfaces=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" surfaces=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" surfaces=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" surfaces=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" surfaces=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" surfaces="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" surfaces="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" surfaces="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" surfaces="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" surfaces="-1" />
<cell id="22" universe="1" material="2" surfaces="1 -2" />
<cell id="23" universe="1" material="3" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" surfaces="-3" />
<cell id="25" universe="2" material="2" surfaces="3 -4" />
<cell id="26" universe="2" material="3" surfaces="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" surfaces="-1" />
<cell id="28" universe="3" material="2" surfaces="1 -2" />
<cell id="29" universe="3" material="4" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" surfaces="-3" />
<cell id="31" universe="4" material="2" surfaces="3 -4" />
<cell id="32" universe="4" material="4" surfaces="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" surfaces="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" surfaces="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" surfaces="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" surfaces="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

272
tests/test_score_flux_yn/materials.xml Normal file
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@ -0,0 +1,272 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U-234" ao="4.9476e-6" />
<nuclide name="U-235" ao="4.8218e-4" />
<nuclide name="U-236" ao="9.0402e-5" />
<nuclide name="U-238" ao="2.1504e-2" />
<nuclide name="Np-237" ao="7.3733e-6" />
<nuclide name="Pu-238" ao="1.5148e-6" />
<nuclide name="Pu-239" ao="1.3955e-4" />
<nuclide name="Pu-240" ao="3.4405e-5" />
<nuclide name="Pu-241" ao="2.1439e-5" />
<nuclide name="Pu-242" ao="3.7422e-6" />
<nuclide name="Am-241" ao="4.5041e-7" />
<nuclide name="Am-242m" ao="9.2301e-9" />
<nuclide name="Am-243" ao="4.7878e-7" />
<nuclide name="Cm-242" ao="1.0485e-7" />
<nuclide name="Cm-243" ao="1.4268e-9" />
<nuclide name="Cm-244" ao="8.8756e-8" />
<nuclide name="Cm-245" ao="3.5285e-9" />
<nuclide name="Mo-95" ao="2.6497e-5" />
<nuclide name="Tc-99" ao="3.2772e-5" />
<nuclide name="Ru-101" ao="3.0742e-5" />
<nuclide name="Ru-103" ao="2.3505e-6" />
<nuclide name="Ag-109" ao="2.0009e-6" />
<nuclide name="Xe-135" ao="1.0801e-8" />
<nuclide name="Cs-133" ao="3.4612e-5" />
<nuclide name="Nd-143" ao="2.6078e-5" />
<nuclide name="Nd-145" ao="1.9898e-5" />
<nuclide name="Sm-147" ao="1.6128e-6" />
<nuclide name="Sm-149" ao="1.1627e-7" />
<nuclide name="Sm-150" ao="7.1727e-6" />
<nuclide name="Sm-151" ao="5.4947e-7" />
<nuclide name="Sm-152" ao="3.0221e-6" />
<nuclide name="Eu-153" ao="2.6209e-6" />
<nuclide name="Gd-155" ao="1.5369e-9" />
<nuclide name="O-16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<nuclide name="Zr-90" ao="0.5145" />
<nuclide name="Zr-91" ao="0.1122" />
<nuclide name="Zr-92" ao="0.1715" />
<nuclide name="Zr-94" ao="0.1738" />
<nuclide name="Zr-96" ao="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-5" />
<nuclide name="B-11" wo="1.40499e-4" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.0182870" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-5" />
<nuclide name="B-11" wo="1.26481e-4" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-6" />
<nuclide name="B-11" wo="1.68974e-5" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.0197940" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-5" />
<nuclide name="B-11" wo="3.59854e-4" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H-1" wo="0.0358870" />
<nuclide name="O-16" wo="0.2847761" />
<nuclide name="B-10" wo="1.15699e-4" />
<nuclide name="B-11" wo="5.27075e-4" />
<nuclide name="Fe-54" wo="0.02644016154" />
<nuclide name="Fe-56" wo="0.43037146399" />
<nuclide name="Fe-57" wo="0.0101152584" />
<nuclide name="Fe-58" wo="0.00137211607" />
<nuclide name="Ni-58" wo="0.04104621835" />
<nuclide name="Ni-60" wo="0.0163554502" />
<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
<nuclide name="Si-28" wo="0.006234853554" />
<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-5" />
<nuclide name="B-11" wo="2.39272e-4" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-5" />
<nuclide name="B-11" wo="4.30120e-4" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

44
tests/test_score_flux_yn/results.py Normal file
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@ -0,0 +1,44 @@
#!/usr/bin/env python
import sys
import numpy as np
# import statepoint
sys.path.append('../../src/utils')
import statepoint
# read in statepoint file
if len(sys.argv) > 1:
sp = statepoint.StatePoint(sys.argv[1])
else:
sp = statepoint.StatePoint('statepoint.10.binary')
sp.read_results()
# extract tally results and convert to vector
results1 = sp.tallies[0].results
shape1 = results1.shape
size1 = (np.product(shape1))
results1 = np.reshape(results1, size1)
results2 = sp.tallies[1].results
shape2 = results2.shape
size2 = (np.product(shape2))
results2 = np.reshape(results2, size2)
# set up output string
outstr = ''
# write out k-combined
outstr += 'k-combined:\n'
outstr += "{0:12.6E} {1:12.6E}\n".format(sp.k_combined[0], sp.k_combined[1])
# write out tally results
outstr += 'tally 1:\n'
for item in results1:
outstr += "{0:12.6E}\n".format(item)
outstr += 'tally 2:\n'
for item in results2:
outstr += "{0:12.6E}\n".format(item)
# write results to file
with open('results_test.dat','w') as fh:
fh.write(outstr)

448
tests/test_score_flux_yn/results_true.dat Normal file
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k-combined:
9.785262E-01 2.895177E-02
tally 1:
2.435729E+01
1.203987E+02
8.194681E+00
1.380086E+01
3.940735E+01
3.173417E+02
3.867197E+01
3.002989E+02
1.337306E+01
3.597709E+01
6.603960E+01
8.773418E+02
tally 2:
2.435729E+01
1.203987E+02
-1.312433E-01
2.122879E-01
2.116196E-01
6.066255E-02
-5.313614E-01
2.706195E-01
-1.075684E-01
7.055293E-02
1.243217E-01
4.159849E-02
2.468823E-01
1.768096E-01
-1.123588E+00
3.763177E-01
-1.648770E-02
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19
tests/test_score_flux_yn/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

14
tests/test_score_flux_yn/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="21 22 23 27 28 29" />
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="21 22 23 27 28 29" />
<scores>flux-y5</scores>
</tally>
</tallies>

62
tests/test_score_flux_yn/test_score_flux_yn.py Normal file
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#!/usr/bin/env python
import os
from subprocess import Popen, STDOUT, PIPE, call
import filecmp
import glob
from optparse import OptionParser
parser = OptionParser()
parser.add_option('--mpi_exec', dest='mpi_exec', default='')
parser.add_option('--mpi_np', dest='mpi_np', default='3')
parser.add_option('--exe', dest='exe')
(opts, args) = parser.parse_args()
cwd = os.getcwd()
def test_run():
if opts.mpi_exec != '':
proc = Popen([opts.mpi_exec, '-np', opts.mpi_np, opts.exe, cwd],
stderr=STDOUT, stdout=PIPE)
else:
proc = Popen([opts.exe, cwd], stderr=STDOUT, stdout=PIPE)
print(proc.communicate()[0])
returncode = proc.returncode
assert returncode == 0, 'OpenMC did not exit successfully.'
def test_created_statepoint():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
assert len(statepoint) == 1, 'Either multiple or no statepoint files exist.'
assert statepoint[0].endswith('binary') or statepoint[0].endswith('h5'),\
'Statepoint file is not a binary or hdf5 file.'
def test_output_exists():
assert os.path.exists(os.path.join(cwd, 'tallies.out')), 'Tally output file does not exist.'
def test_results():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
call(['python', 'results.py', statepoint[0]])
compare = filecmp.cmp('results_test.dat', 'results_true.dat')
if not compare:
os.rename('results_test.dat', 'results_error.dat')
assert compare, 'Results do not agree.'
def teardown():
output = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
output.append(os.path.join(cwd, 'tallies.out'))
output.append(os.path.join(cwd, 'results_test.dat'))
for f in output:
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
# test for openmc executable
if opts.exe is None:
raise Exception('Must specify OpenMC executable from command line with --exe.')
# run tests
test_run()
test_created_statepoint()
test_output_exists()
test_results()
teardown()

185
tests/test_score_nuscatter_n/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" surfaces=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" surfaces=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" surfaces=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" surfaces=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" surfaces=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" surfaces=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" surfaces=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" surfaces=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" surfaces="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" surfaces="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" surfaces="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" surfaces="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" surfaces="-1" />
<cell id="22" universe="1" material="2" surfaces="1 -2" />
<cell id="23" universe="1" material="3" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" surfaces="-3" />
<cell id="25" universe="2" material="2" surfaces="3 -4" />
<cell id="26" universe="2" material="3" surfaces="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" surfaces="-1" />
<cell id="28" universe="3" material="2" surfaces="1 -2" />
<cell id="29" universe="3" material="4" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" surfaces="-3" />
<cell id="31" universe="4" material="2" surfaces="3 -4" />
<cell id="32" universe="4" material="4" surfaces="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" surfaces="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" surfaces="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" surfaces="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" surfaces="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
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5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
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7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
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7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
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7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

272
tests/test_score_nuscatter_n/materials.xml Normal file
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@ -0,0 +1,272 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U-234" ao="4.9476e-6" />
<nuclide name="U-235" ao="4.8218e-4" />
<nuclide name="U-236" ao="9.0402e-5" />
<nuclide name="U-238" ao="2.1504e-2" />
<nuclide name="Np-237" ao="7.3733e-6" />
<nuclide name="Pu-238" ao="1.5148e-6" />
<nuclide name="Pu-239" ao="1.3955e-4" />
<nuclide name="Pu-240" ao="3.4405e-5" />
<nuclide name="Pu-241" ao="2.1439e-5" />
<nuclide name="Pu-242" ao="3.7422e-6" />
<nuclide name="Am-241" ao="4.5041e-7" />
<nuclide name="Am-242m" ao="9.2301e-9" />
<nuclide name="Am-243" ao="4.7878e-7" />
<nuclide name="Cm-242" ao="1.0485e-7" />
<nuclide name="Cm-243" ao="1.4268e-9" />
<nuclide name="Cm-244" ao="8.8756e-8" />
<nuclide name="Cm-245" ao="3.5285e-9" />
<nuclide name="Mo-95" ao="2.6497e-5" />
<nuclide name="Tc-99" ao="3.2772e-5" />
<nuclide name="Ru-101" ao="3.0742e-5" />
<nuclide name="Ru-103" ao="2.3505e-6" />
<nuclide name="Ag-109" ao="2.0009e-6" />
<nuclide name="Xe-135" ao="1.0801e-8" />
<nuclide name="Cs-133" ao="3.4612e-5" />
<nuclide name="Nd-143" ao="2.6078e-5" />
<nuclide name="Nd-145" ao="1.9898e-5" />
<nuclide name="Sm-147" ao="1.6128e-6" />
<nuclide name="Sm-149" ao="1.1627e-7" />
<nuclide name="Sm-150" ao="7.1727e-6" />
<nuclide name="Sm-151" ao="5.4947e-7" />
<nuclide name="Sm-152" ao="3.0221e-6" />
<nuclide name="Eu-153" ao="2.6209e-6" />
<nuclide name="Gd-155" ao="1.5369e-9" />
<nuclide name="O-16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<nuclide name="Zr-90" ao="0.5145" />
<nuclide name="Zr-91" ao="0.1122" />
<nuclide name="Zr-92" ao="0.1715" />
<nuclide name="Zr-94" ao="0.1738" />
<nuclide name="Zr-96" ao="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-5" />
<nuclide name="B-11" wo="1.40499e-4" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.0182870" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-5" />
<nuclide name="B-11" wo="1.26481e-4" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-6" />
<nuclide name="B-11" wo="1.68974e-5" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.0197940" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-5" />
<nuclide name="B-11" wo="3.59854e-4" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H-1" wo="0.0358870" />
<nuclide name="O-16" wo="0.2847761" />
<nuclide name="B-10" wo="1.15699e-4" />
<nuclide name="B-11" wo="5.27075e-4" />
<nuclide name="Fe-54" wo="0.02644016154" />
<nuclide name="Fe-56" wo="0.43037146399" />
<nuclide name="Fe-57" wo="0.0101152584" />
<nuclide name="Fe-58" wo="0.00137211607" />
<nuclide name="Ni-58" wo="0.04104621835" />
<nuclide name="Ni-60" wo="0.0163554502" />
<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
<nuclide name="Si-28" wo="0.006234853554" />
<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-5" />
<nuclide name="B-11" wo="2.39272e-4" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-5" />
<nuclide name="B-11" wo="4.30120e-4" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

37
tests/test_score_nuscatter_n/results.py Normal file
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#!/usr/bin/env python
import sys
import numpy as np
# import statepoint
sys.path.append('../../src/utils')
import statepoint
# read in statepoint file
if len(sys.argv) > 1:
sp = statepoint.StatePoint(sys.argv[1])
else:
sp = statepoint.StatePoint('statepoint.10.binary')
sp.read_results()
# extract tally results and convert to vector
results = sp.tallies[0].results
shape = results.shape
size = (np.product(shape))
results = np.reshape(results, size)
# set up output string
outstr = ''
# write out k-combined
outstr += 'k-combined:\n'
outstr += "{0:12.6E} {1:12.6E}\n".format(sp.k_combined[0], sp.k_combined[1])
# write out tally results
outstr += 'tallies:\n'
for item in results:
outstr += "{0:12.6E}\n".format(item)
# write results to file
with open('results_test.dat','w') as fh:
fh.write(outstr)

33
tests/test_score_nuscatter_n/results_true.dat Normal file
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k-combined:
9.785262E-01 2.895177E-02
tallies:
9.630000E+00
1.882770E+01
9.951694E-01
2.306142E-01
4.578746E-01
5.623761E-02
4.846244E-01
6.415248E-02
1.908107E-01
1.203246E-02
1.920000E+00
7.570000E-01
2.543372E-01
1.948219E-02
1.781533E-01
7.666342E-03
2.613666E-02
1.105500E-03
-1.067567E-01
3.627605E-03
3.114000E+01
1.988874E+02
1.607479E+01
5.265956E+01
5.942231E+00
7.358984E+00
5.014911E-01
1.018317E-01
-7.566804E-01
1.535164E-01

19
tests/test_score_nuscatter_n/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

9
tests/test_score_nuscatter_n/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="21 22 23" />
<scores>nu-scatter nu-scatter-1 nu-scatter-2 nu-scatter-3 nu-scatter-4</scores>
</tally>
</tallies>

62
tests/test_score_nuscatter_n/test_score_nuscatter_n.py Normal file
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#!/usr/bin/env python
import os
from subprocess import Popen, STDOUT, PIPE, call
import filecmp
import glob
from optparse import OptionParser
parser = OptionParser()
parser.add_option('--mpi_exec', dest='mpi_exec', default='')
parser.add_option('--mpi_np', dest='mpi_np', default='3')
parser.add_option('--exe', dest='exe')
(opts, args) = parser.parse_args()
cwd = os.getcwd()
def test_run():
if opts.mpi_exec != '':
proc = Popen([opts.mpi_exec, '-np', opts.mpi_np, opts.exe, cwd],
stderr=STDOUT, stdout=PIPE)
else:
proc = Popen([opts.exe, cwd], stderr=STDOUT, stdout=PIPE)
print(proc.communicate()[0])
returncode = proc.returncode
assert returncode == 0, 'OpenMC did not exit successfully.'
def test_created_statepoint():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
assert len(statepoint) == 1, 'Either multiple or no statepoint files exist.'
assert statepoint[0].endswith('binary') or statepoint[0].endswith('h5'),\
'Statepoint file is not a binary or hdf5 file.'
def test_output_exists():
assert os.path.exists(os.path.join(cwd, 'tallies.out')), 'Tally output file does not exist.'
def test_results():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
call(['python', 'results.py', statepoint[0]])
compare = filecmp.cmp('results_test.dat', 'results_true.dat')
if not compare:
os.rename('results_test.dat', 'results_error.dat')
assert compare, 'Results do not agree.'
def teardown():
output = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
output.append(os.path.join(cwd, 'tallies.out'))
output.append(os.path.join(cwd, 'results_test.dat'))
for f in output:
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
# test for openmc executable
if opts.exe is None:
raise Exception('Must specify OpenMC executable from command line with --exe.')
# run tests
test_run()
test_created_statepoint()
test_output_exists()
test_results()
teardown()

185
tests/test_score_nuscatter_pn/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" surfaces=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" surfaces=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" surfaces=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" surfaces=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" surfaces=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" surfaces=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" surfaces=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" surfaces=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" surfaces="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" surfaces="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" surfaces="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" surfaces="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" surfaces="-1" />
<cell id="22" universe="1" material="2" surfaces="1 -2" />
<cell id="23" universe="1" material="3" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" surfaces="-3" />
<cell id="25" universe="2" material="2" surfaces="3 -4" />
<cell id="26" universe="2" material="3" surfaces="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" surfaces="-1" />
<cell id="28" universe="3" material="2" surfaces="1 -2" />
<cell id="29" universe="3" material="4" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" surfaces="-3" />
<cell id="31" universe="4" material="2" surfaces="3 -4" />
<cell id="32" universe="4" material="4" surfaces="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" surfaces="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" surfaces="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" surfaces="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" surfaces="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

272
tests/test_score_nuscatter_pn/materials.xml Normal file
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@ -0,0 +1,272 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U-234" ao="4.9476e-6" />
<nuclide name="U-235" ao="4.8218e-4" />
<nuclide name="U-236" ao="9.0402e-5" />
<nuclide name="U-238" ao="2.1504e-2" />
<nuclide name="Np-237" ao="7.3733e-6" />
<nuclide name="Pu-238" ao="1.5148e-6" />
<nuclide name="Pu-239" ao="1.3955e-4" />
<nuclide name="Pu-240" ao="3.4405e-5" />
<nuclide name="Pu-241" ao="2.1439e-5" />
<nuclide name="Pu-242" ao="3.7422e-6" />
<nuclide name="Am-241" ao="4.5041e-7" />
<nuclide name="Am-242m" ao="9.2301e-9" />
<nuclide name="Am-243" ao="4.7878e-7" />
<nuclide name="Cm-242" ao="1.0485e-7" />
<nuclide name="Cm-243" ao="1.4268e-9" />
<nuclide name="Cm-244" ao="8.8756e-8" />
<nuclide name="Cm-245" ao="3.5285e-9" />
<nuclide name="Mo-95" ao="2.6497e-5" />
<nuclide name="Tc-99" ao="3.2772e-5" />
<nuclide name="Ru-101" ao="3.0742e-5" />
<nuclide name="Ru-103" ao="2.3505e-6" />
<nuclide name="Ag-109" ao="2.0009e-6" />
<nuclide name="Xe-135" ao="1.0801e-8" />
<nuclide name="Cs-133" ao="3.4612e-5" />
<nuclide name="Nd-143" ao="2.6078e-5" />
<nuclide name="Nd-145" ao="1.9898e-5" />
<nuclide name="Sm-147" ao="1.6128e-6" />
<nuclide name="Sm-149" ao="1.1627e-7" />
<nuclide name="Sm-150" ao="7.1727e-6" />
<nuclide name="Sm-151" ao="5.4947e-7" />
<nuclide name="Sm-152" ao="3.0221e-6" />
<nuclide name="Eu-153" ao="2.6209e-6" />
<nuclide name="Gd-155" ao="1.5369e-9" />
<nuclide name="O-16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<nuclide name="Zr-90" ao="0.5145" />
<nuclide name="Zr-91" ao="0.1122" />
<nuclide name="Zr-92" ao="0.1715" />
<nuclide name="Zr-94" ao="0.1738" />
<nuclide name="Zr-96" ao="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-5" />
<nuclide name="B-11" wo="1.40499e-4" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.0182870" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-5" />
<nuclide name="B-11" wo="1.26481e-4" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-6" />
<nuclide name="B-11" wo="1.68974e-5" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.0197940" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-5" />
<nuclide name="B-11" wo="3.59854e-4" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H-1" wo="0.0358870" />
<nuclide name="O-16" wo="0.2847761" />
<nuclide name="B-10" wo="1.15699e-4" />
<nuclide name="B-11" wo="5.27075e-4" />
<nuclide name="Fe-54" wo="0.02644016154" />
<nuclide name="Fe-56" wo="0.43037146399" />
<nuclide name="Fe-57" wo="0.0101152584" />
<nuclide name="Fe-58" wo="0.00137211607" />
<nuclide name="Ni-58" wo="0.04104621835" />
<nuclide name="Ni-60" wo="0.0163554502" />
<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
<nuclide name="Si-28" wo="0.006234853554" />
<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-5" />
<nuclide name="B-11" wo="2.39272e-4" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-5" />
<nuclide name="B-11" wo="4.30120e-4" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

44
tests/test_score_nuscatter_pn/results.py Normal file
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@ -0,0 +1,44 @@
#!/usr/bin/env python
import sys
import numpy as np
# import statepoint
sys.path.append('../../src/utils')
import statepoint
# read in statepoint file
if len(sys.argv) > 1:
sp = statepoint.StatePoint(sys.argv[1])
else:
sp = statepoint.StatePoint('statepoint.10.binary')
sp.read_results()
# extract tally results and convert to vector
results1 = sp.tallies[0].results
shape1 = results1.shape
size1 = (np.product(shape1))
results1 = np.reshape(results1, size1)
results2 = sp.tallies[1].results
shape2 = results2.shape
size2 = (np.product(shape2))
results2 = np.reshape(results2, size2)
# set up output string
outstr = ''
# write out k-combined
outstr += 'k-combined:\n'
outstr += "{0:12.6E} {1:12.6E}\n".format(sp.k_combined[0], sp.k_combined[1])
# write out tally results
outstr += 'tally 1:\n'
for item in results1:
outstr += "{0:12.6E}\n".format(item)
outstr += 'tally 2:\n'
for item in results2:
outstr += "{0:12.6E}\n".format(item)
# write results to file
with open('results_test.dat','w') as fh:
fh.write(outstr)

24
tests/test_score_nuscatter_pn/results_true.dat Normal file
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k-combined:
9.785262E-01 2.895177E-02
tally 1:
9.630000E+00
1.882770E+01
9.951694E-01
2.306142E-01
4.578746E-01
5.623761E-02
4.846244E-01
6.415248E-02
1.908107E-01
1.203246E-02
tally 2:
9.630000E+00
1.882770E+01
9.951694E-01
2.306142E-01
4.578746E-01
5.623761E-02
4.846244E-01
6.415248E-02
1.908107E-01
1.203246E-02

19
tests/test_score_nuscatter_pn/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

14
tests/test_score_nuscatter_pn/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="21" />
<scores>nu-scatter-0 nu-scatter-1 nu-scatter-2 nu-scatter-3 nu-scatter-4</scores>
</tally>
<tally id="2">
<filter type="cell" bins="21" />
<scores>nu-scatter-p4</scores>
</tally>
</tallies>

62
tests/test_score_nuscatter_pn/test_score_nuscatter_pn.py Normal file
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#!/usr/bin/env python
import os
from subprocess import Popen, STDOUT, PIPE, call
import filecmp
import glob
from optparse import OptionParser
parser = OptionParser()
parser.add_option('--mpi_exec', dest='mpi_exec', default='')
parser.add_option('--mpi_np', dest='mpi_np', default='3')
parser.add_option('--exe', dest='exe')
(opts, args) = parser.parse_args()
cwd = os.getcwd()
def test_run():
if opts.mpi_exec != '':
proc = Popen([opts.mpi_exec, '-np', opts.mpi_np, opts.exe, cwd],
stderr=STDOUT, stdout=PIPE)
else:
proc = Popen([opts.exe, cwd], stderr=STDOUT, stdout=PIPE)
print(proc.communicate()[0])
returncode = proc.returncode
assert returncode == 0, 'OpenMC did not exit successfully.'
def test_created_statepoint():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
assert len(statepoint) == 1, 'Either multiple or no statepoint files exist.'
assert statepoint[0].endswith('binary') or statepoint[0].endswith('h5'),\
'Statepoint file is not a binary or hdf5 file.'
def test_output_exists():
assert os.path.exists(os.path.join(cwd, 'tallies.out')), 'Tally output file does not exist.'
def test_results():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
call(['python', 'results.py', statepoint[0]])
compare = filecmp.cmp('results_test.dat', 'results_true.dat')
if not compare:
os.rename('results_test.dat', 'results_error.dat')
assert compare, 'Results do not agree.'
def teardown():
output = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
output.append(os.path.join(cwd, 'tallies.out'))
output.append(os.path.join(cwd, 'results_test.dat'))
for f in output:
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
# test for openmc executable
if opts.exe is None:
raise Exception('Must specify OpenMC executable from command line with --exe.')
# run tests
test_run()
test_created_statepoint()
test_output_exists()
test_results()
teardown()

185
tests/test_score_nuscatter_yn/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" surfaces=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" surfaces=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" surfaces=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" surfaces=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" surfaces=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" surfaces=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" surfaces=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" surfaces=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" surfaces="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" surfaces="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" surfaces="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" surfaces="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" surfaces="-1" />
<cell id="22" universe="1" material="2" surfaces="1 -2" />
<cell id="23" universe="1" material="3" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" surfaces="-3" />
<cell id="25" universe="2" material="2" surfaces="3 -4" />
<cell id="26" universe="2" material="3" surfaces="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" surfaces="-1" />
<cell id="28" universe="3" material="2" surfaces="1 -2" />
<cell id="29" universe="3" material="4" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" surfaces="-3" />
<cell id="31" universe="4" material="2" surfaces="3 -4" />
<cell id="32" universe="4" material="4" surfaces="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" surfaces="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" surfaces="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" surfaces="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" surfaces="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

272
tests/test_score_nuscatter_yn/materials.xml Normal file
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<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U-234" ao="4.9476e-6" />
<nuclide name="U-235" ao="4.8218e-4" />
<nuclide name="U-236" ao="9.0402e-5" />
<nuclide name="U-238" ao="2.1504e-2" />
<nuclide name="Np-237" ao="7.3733e-6" />
<nuclide name="Pu-238" ao="1.5148e-6" />
<nuclide name="Pu-239" ao="1.3955e-4" />
<nuclide name="Pu-240" ao="3.4405e-5" />
<nuclide name="Pu-241" ao="2.1439e-5" />
<nuclide name="Pu-242" ao="3.7422e-6" />
<nuclide name="Am-241" ao="4.5041e-7" />
<nuclide name="Am-242m" ao="9.2301e-9" />
<nuclide name="Am-243" ao="4.7878e-7" />
<nuclide name="Cm-242" ao="1.0485e-7" />
<nuclide name="Cm-243" ao="1.4268e-9" />
<nuclide name="Cm-244" ao="8.8756e-8" />
<nuclide name="Cm-245" ao="3.5285e-9" />
<nuclide name="Mo-95" ao="2.6497e-5" />
<nuclide name="Tc-99" ao="3.2772e-5" />
<nuclide name="Ru-101" ao="3.0742e-5" />
<nuclide name="Ru-103" ao="2.3505e-6" />
<nuclide name="Ag-109" ao="2.0009e-6" />
<nuclide name="Xe-135" ao="1.0801e-8" />
<nuclide name="Cs-133" ao="3.4612e-5" />
<nuclide name="Nd-143" ao="2.6078e-5" />
<nuclide name="Nd-145" ao="1.9898e-5" />
<nuclide name="Sm-147" ao="1.6128e-6" />
<nuclide name="Sm-149" ao="1.1627e-7" />
<nuclide name="Sm-150" ao="7.1727e-6" />
<nuclide name="Sm-151" ao="5.4947e-7" />
<nuclide name="Sm-152" ao="3.0221e-6" />
<nuclide name="Eu-153" ao="2.6209e-6" />
<nuclide name="Gd-155" ao="1.5369e-9" />
<nuclide name="O-16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<nuclide name="Zr-90" ao="0.5145" />
<nuclide name="Zr-91" ao="0.1122" />
<nuclide name="Zr-92" ao="0.1715" />
<nuclide name="Zr-94" ao="0.1738" />
<nuclide name="Zr-96" ao="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-5" />
<nuclide name="B-11" wo="1.40499e-4" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.0182870" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-5" />
<nuclide name="B-11" wo="1.26481e-4" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-6" />
<nuclide name="B-11" wo="1.68974e-5" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.0197940" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-5" />
<nuclide name="B-11" wo="3.59854e-4" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H-1" wo="0.0358870" />
<nuclide name="O-16" wo="0.2847761" />
<nuclide name="B-10" wo="1.15699e-4" />
<nuclide name="B-11" wo="5.27075e-4" />
<nuclide name="Fe-54" wo="0.02644016154" />
<nuclide name="Fe-56" wo="0.43037146399" />
<nuclide name="Fe-57" wo="0.0101152584" />
<nuclide name="Fe-58" wo="0.00137211607" />
<nuclide name="Ni-58" wo="0.04104621835" />
<nuclide name="Ni-60" wo="0.0163554502" />
<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
<nuclide name="Si-28" wo="0.006234853554" />
<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-5" />
<nuclide name="B-11" wo="2.39272e-4" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-5" />
<nuclide name="B-11" wo="4.30120e-4" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

44
tests/test_score_nuscatter_yn/results.py Normal file
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#!/usr/bin/env python
import sys
import numpy as np
# import statepoint
sys.path.append('../../src/utils')
import statepoint
# read in statepoint file
if len(sys.argv) > 1:
sp = statepoint.StatePoint(sys.argv[1])
else:
sp = statepoint.StatePoint('statepoint.10.binary')
sp.read_results()
# extract tally results and convert to vector
results1 = sp.tallies[0].results
shape1 = results1.shape
size1 = (np.product(shape1))
results1 = np.reshape(results1, size1)
results2 = sp.tallies[1].results
shape2 = results2.shape
size2 = (np.product(shape2))
results2 = np.reshape(results2, size2)
# set up output string
outstr = ''
# write out k-combined
outstr += 'k-combined:\n'
outstr += "{0:12.6E} {1:12.6E}\n".format(sp.k_combined[0], sp.k_combined[1])
# write out tally results
outstr += 'tally 1:\n'
for item in results1:
outstr += "{0:12.6E}\n".format(item)
outstr += 'tally 2:\n'
for item in results2:
outstr += "{0:12.6E}\n".format(item)
# write results to file
with open('results_test.dat','w') as fh:
fh.write(outstr)

38
tests/test_score_nuscatter_yn/results_true.dat Normal file
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k-combined:
9.785262E-01 2.895177E-02
tally 1:
9.630000E+00
1.882770E+01
tally 2:
9.630000E+00
1.882770E+01
-3.859107E-02
5.633136E-03
1.605692E-01
1.156085E-02
-3.977190E-02
6.818184E-03
3.522369E-02
3.789031E-03
-7.407836E-02
2.699128E-03
-2.238973E-02
4.031197E-03
-8.969310E-02
2.769455E-03
4.330738E-02
1.714798E-03
-2.173918E-03
4.710249E-03
2.499041E-02
1.104051E-03
-7.071751E-02
2.855396E-03
-5.031274E-02
1.551567E-03
-8.277227E-02
2.137523E-03
-1.616867E-02
1.338600E-03
-1.497058E-02
2.014934E-03

19
tests/test_score_nuscatter_yn/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

14
tests/test_score_nuscatter_yn/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="21" />
<scores>nu-scatter-0</scores>
</tally>
<tally id="2">
<filter type="cell" bins="21" />
<scores>nu-scatter-y3</scores>
</tally>
</tallies>

62
tests/test_score_nuscatter_yn/test_score_nuscatter_yn.py Normal file
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#!/usr/bin/env python
import os
from subprocess import Popen, STDOUT, PIPE, call
import filecmp
import glob
from optparse import OptionParser
parser = OptionParser()
parser.add_option('--mpi_exec', dest='mpi_exec', default='')
parser.add_option('--mpi_np', dest='mpi_np', default='3')
parser.add_option('--exe', dest='exe')
(opts, args) = parser.parse_args()
cwd = os.getcwd()
def test_run():
if opts.mpi_exec != '':
proc = Popen([opts.mpi_exec, '-np', opts.mpi_np, opts.exe, cwd],
stderr=STDOUT, stdout=PIPE)
else:
proc = Popen([opts.exe, cwd], stderr=STDOUT, stdout=PIPE)
print(proc.communicate()[0])
returncode = proc.returncode
assert returncode == 0, 'OpenMC did not exit successfully.'
def test_created_statepoint():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
assert len(statepoint) == 1, 'Either multiple or no statepoint files exist.'
assert statepoint[0].endswith('binary') or statepoint[0].endswith('h5'),\
'Statepoint file is not a binary or hdf5 file.'
def test_output_exists():
assert os.path.exists(os.path.join(cwd, 'tallies.out')), 'Tally output file does not exist.'
def test_results():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
call(['python', 'results.py', statepoint[0]])
compare = filecmp.cmp('results_test.dat', 'results_true.dat')
if not compare:
os.rename('results_test.dat', 'results_error.dat')
assert compare, 'Results do not agree.'
def teardown():
output = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
output.append(os.path.join(cwd, 'tallies.out'))
output.append(os.path.join(cwd, 'results_test.dat'))
for f in output:
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
# test for openmc executable
if opts.exe is None:
raise Exception('Must specify OpenMC executable from command line with --exe.')
# run tests
test_run()
test_created_statepoint()
test_output_exists()
test_results()
teardown()

185
tests/test_score_scatter_yn/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" surfaces=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" surfaces=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" surfaces=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" surfaces=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" surfaces=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" surfaces=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" surfaces=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" surfaces=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" surfaces="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" surfaces="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" surfaces="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" surfaces="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" surfaces="-1" />
<cell id="22" universe="1" material="2" surfaces="1 -2" />
<cell id="23" universe="1" material="3" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" surfaces="-3" />
<cell id="25" universe="2" material="2" surfaces="3 -4" />
<cell id="26" universe="2" material="3" surfaces="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" surfaces="-1" />
<cell id="28" universe="3" material="2" surfaces="1 -2" />
<cell id="29" universe="3" material="4" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" surfaces="-3" />
<cell id="31" universe="4" material="2" surfaces="3 -4" />
<cell id="32" universe="4" material="4" surfaces="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" surfaces="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" surfaces="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" surfaces="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" surfaces="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

272
tests/test_score_scatter_yn/materials.xml Normal file
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<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U-234" ao="4.9476e-6" />
<nuclide name="U-235" ao="4.8218e-4" />
<nuclide name="U-236" ao="9.0402e-5" />
<nuclide name="U-238" ao="2.1504e-2" />
<nuclide name="Np-237" ao="7.3733e-6" />
<nuclide name="Pu-238" ao="1.5148e-6" />
<nuclide name="Pu-239" ao="1.3955e-4" />
<nuclide name="Pu-240" ao="3.4405e-5" />
<nuclide name="Pu-241" ao="2.1439e-5" />
<nuclide name="Pu-242" ao="3.7422e-6" />
<nuclide name="Am-241" ao="4.5041e-7" />
<nuclide name="Am-242m" ao="9.2301e-9" />
<nuclide name="Am-243" ao="4.7878e-7" />
<nuclide name="Cm-242" ao="1.0485e-7" />
<nuclide name="Cm-243" ao="1.4268e-9" />
<nuclide name="Cm-244" ao="8.8756e-8" />
<nuclide name="Cm-245" ao="3.5285e-9" />
<nuclide name="Mo-95" ao="2.6497e-5" />
<nuclide name="Tc-99" ao="3.2772e-5" />
<nuclide name="Ru-101" ao="3.0742e-5" />
<nuclide name="Ru-103" ao="2.3505e-6" />
<nuclide name="Ag-109" ao="2.0009e-6" />
<nuclide name="Xe-135" ao="1.0801e-8" />
<nuclide name="Cs-133" ao="3.4612e-5" />
<nuclide name="Nd-143" ao="2.6078e-5" />
<nuclide name="Nd-145" ao="1.9898e-5" />
<nuclide name="Sm-147" ao="1.6128e-6" />
<nuclide name="Sm-149" ao="1.1627e-7" />
<nuclide name="Sm-150" ao="7.1727e-6" />
<nuclide name="Sm-151" ao="5.4947e-7" />
<nuclide name="Sm-152" ao="3.0221e-6" />
<nuclide name="Eu-153" ao="2.6209e-6" />
<nuclide name="Gd-155" ao="1.5369e-9" />
<nuclide name="O-16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<nuclide name="Zr-90" ao="0.5145" />
<nuclide name="Zr-91" ao="0.1122" />
<nuclide name="Zr-92" ao="0.1715" />
<nuclide name="Zr-94" ao="0.1738" />
<nuclide name="Zr-96" ao="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-5" />
<nuclide name="B-11" wo="1.40499e-4" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.0182870" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-5" />
<nuclide name="B-11" wo="1.26481e-4" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-6" />
<nuclide name="B-11" wo="1.68974e-5" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.0197940" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-5" />
<nuclide name="B-11" wo="3.59854e-4" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H-1" wo="0.0358870" />
<nuclide name="O-16" wo="0.2847761" />
<nuclide name="B-10" wo="1.15699e-4" />
<nuclide name="B-11" wo="5.27075e-4" />
<nuclide name="Fe-54" wo="0.02644016154" />
<nuclide name="Fe-56" wo="0.43037146399" />
<nuclide name="Fe-57" wo="0.0101152584" />
<nuclide name="Fe-58" wo="0.00137211607" />
<nuclide name="Ni-58" wo="0.04104621835" />
<nuclide name="Ni-60" wo="0.0163554502" />
<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
<nuclide name="Si-28" wo="0.006234853554" />
<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-5" />
<nuclide name="B-11" wo="2.39272e-4" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-5" />
<nuclide name="B-11" wo="4.30120e-4" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

44
tests/test_score_scatter_yn/results.py Normal file
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#!/usr/bin/env python
import sys
import numpy as np
# import statepoint
sys.path.append('../../src/utils')
import statepoint
# read in statepoint file
if len(sys.argv) > 1:
sp = statepoint.StatePoint(sys.argv[1])
else:
sp = statepoint.StatePoint('statepoint.10.binary')
sp.read_results()
# extract tally results and convert to vector
results1 = sp.tallies[0].results
shape1 = results1.shape
size1 = (np.product(shape1))
results1 = np.reshape(results1, size1)
results2 = sp.tallies[1].results
shape2 = results2.shape
size2 = (np.product(shape2))
results2 = np.reshape(results2, size2)
# set up output string
outstr = ''
# write out k-combined
outstr += 'k-combined:\n'
outstr += "{0:12.6E} {1:12.6E}\n".format(sp.k_combined[0], sp.k_combined[1])
# write out tally results
outstr += 'tally 1:\n'
for item in results1:
outstr += "{0:12.6E}\n".format(item)
outstr += 'tally 2:\n'
for item in results2:
outstr += "{0:12.6E}\n".format(item)
# write results to file
with open('results_test.dat','w') as fh:
fh.write(outstr)

56
tests/test_score_scatter_yn/results_true.dat Normal file
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k-combined:
9.785262E-01 2.895177E-02
tally 1:
9.630000E+00
1.882770E+01
tally 2:
9.630000E+00
1.882770E+01
-3.859107E-02
5.633136E-03
1.605692E-01
1.156085E-02
-3.977190E-02
6.818184E-03
3.522369E-02
3.789031E-03
-7.407836E-02
2.699128E-03
-2.238973E-02
4.031197E-03
-8.969310E-02
2.769455E-03
4.330738E-02
1.714798E-03
-2.173918E-03
4.710249E-03
2.499041E-02
1.104051E-03
-7.071751E-02
2.855396E-03
-5.031274E-02
1.551567E-03
-8.277227E-02
2.137523E-03
-1.616867E-02
1.338600E-03
-1.497058E-02
2.014934E-03
-2.683538E-02
1.569513E-03
-4.613955E-03
9.640026E-04
8.947303E-03
3.299483E-04
-8.588404E-03
7.913430E-04
-1.510489E-02
2.519720E-03
3.236471E-03
1.675379E-03
-1.237888E-02
9.699709E-04
4.744373E-02
1.066913E-03
-4.995487E-02
1.125835E-03

19
tests/test_score_scatter_yn/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

15
tests/test_score_scatter_yn/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="21" />
<scores>scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filter type="cell" bins="21" />
<scores>scatter-y4</scores>
</tally>
</tallies>

62
tests/test_score_scatter_yn/test_score_scatter_yn.py Normal file
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#!/usr/bin/env python
import os
from subprocess import Popen, STDOUT, PIPE, call
import filecmp
import glob
from optparse import OptionParser
parser = OptionParser()
parser.add_option('--mpi_exec', dest='mpi_exec', default='')
parser.add_option('--mpi_np', dest='mpi_np', default='3')
parser.add_option('--exe', dest='exe')
(opts, args) = parser.parse_args()
cwd = os.getcwd()
def test_run():
if opts.mpi_exec != '':
proc = Popen([opts.mpi_exec, '-np', opts.mpi_np, opts.exe, cwd],
stderr=STDOUT, stdout=PIPE)
else:
proc = Popen([opts.exe, cwd], stderr=STDOUT, stdout=PIPE)
print(proc.communicate()[0])
returncode = proc.returncode
assert returncode == 0, 'OpenMC did not exit successfully.'
def test_created_statepoint():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
assert len(statepoint) == 1, 'Either multiple or no statepoint files exist.'
assert statepoint[0].endswith('binary') or statepoint[0].endswith('h5'),\
'Statepoint file is not a binary or hdf5 file.'
def test_output_exists():
assert os.path.exists(os.path.join(cwd, 'tallies.out')), 'Tally output file does not exist.'
def test_results():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
call(['python', 'results.py', statepoint[0]])
compare = filecmp.cmp('results_test.dat', 'results_true.dat')
if not compare:
os.rename('results_test.dat', 'results_error.dat')
assert compare, 'Results do not agree.'
def teardown():
output = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
output.append(os.path.join(cwd, 'tallies.out'))
output.append(os.path.join(cwd, 'results_test.dat'))
for f in output:
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
# test for openmc executable
if opts.exe is None:
raise Exception('Must specify OpenMC executable from command line with --exe.')
# run tests
test_run()
test_created_statepoint()
test_output_exists()
test_results()
teardown()

185
tests/test_score_total_yn/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" surfaces=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" surfaces=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" surfaces=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" surfaces=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" surfaces=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" surfaces=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" surfaces=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" surfaces=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" surfaces="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" surfaces="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" surfaces="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" surfaces="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" surfaces="-1" />
<cell id="22" universe="1" material="2" surfaces="1 -2" />
<cell id="23" universe="1" material="3" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" surfaces="-3" />
<cell id="25" universe="2" material="2" surfaces="3 -4" />
<cell id="26" universe="2" material="3" surfaces="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" surfaces="-1" />
<cell id="28" universe="3" material="2" surfaces="1 -2" />
<cell id="29" universe="3" material="4" surfaces="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" surfaces="-3" />
<cell id="31" universe="4" material="2" surfaces="3 -4" />
<cell id="32" universe="4" material="4" surfaces="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" surfaces="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" surfaces="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" surfaces="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" surfaces="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<type>rectangular</type>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<type>rectangular</type>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<width>21.42 21.42</width>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

272
tests/test_score_total_yn/materials.xml Normal file
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@ -0,0 +1,272 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U-234" ao="4.9476e-6" />
<nuclide name="U-235" ao="4.8218e-4" />
<nuclide name="U-236" ao="9.0402e-5" />
<nuclide name="U-238" ao="2.1504e-2" />
<nuclide name="Np-237" ao="7.3733e-6" />
<nuclide name="Pu-238" ao="1.5148e-6" />
<nuclide name="Pu-239" ao="1.3955e-4" />
<nuclide name="Pu-240" ao="3.4405e-5" />
<nuclide name="Pu-241" ao="2.1439e-5" />
<nuclide name="Pu-242" ao="3.7422e-6" />
<nuclide name="Am-241" ao="4.5041e-7" />
<nuclide name="Am-242m" ao="9.2301e-9" />
<nuclide name="Am-243" ao="4.7878e-7" />
<nuclide name="Cm-242" ao="1.0485e-7" />
<nuclide name="Cm-243" ao="1.4268e-9" />
<nuclide name="Cm-244" ao="8.8756e-8" />
<nuclide name="Cm-245" ao="3.5285e-9" />
<nuclide name="Mo-95" ao="2.6497e-5" />
<nuclide name="Tc-99" ao="3.2772e-5" />
<nuclide name="Ru-101" ao="3.0742e-5" />
<nuclide name="Ru-103" ao="2.3505e-6" />
<nuclide name="Ag-109" ao="2.0009e-6" />
<nuclide name="Xe-135" ao="1.0801e-8" />
<nuclide name="Cs-133" ao="3.4612e-5" />
<nuclide name="Nd-143" ao="2.6078e-5" />
<nuclide name="Nd-145" ao="1.9898e-5" />
<nuclide name="Sm-147" ao="1.6128e-6" />
<nuclide name="Sm-149" ao="1.1627e-7" />
<nuclide name="Sm-150" ao="7.1727e-6" />
<nuclide name="Sm-151" ao="5.4947e-7" />
<nuclide name="Sm-152" ao="3.0221e-6" />
<nuclide name="Eu-153" ao="2.6209e-6" />
<nuclide name="Gd-155" ao="1.5369e-9" />
<nuclide name="O-16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<nuclide name="Zr-90" ao="0.5145" />
<nuclide name="Zr-91" ao="0.1122" />
<nuclide name="Zr-92" ao="0.1715" />
<nuclide name="Zr-94" ao="0.1738" />
<nuclide name="Zr-96" ao="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<nuclide name="B-10" ao="6.490e-4" />
<nuclide name="B-11" ao="2.689e-3" />
<sab name="HH2O" xs="71t" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-5" />
<nuclide name="B-11" wo="1.40499e-4" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.0182870" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-5" />
<nuclide name="B-11" wo="1.26481e-4" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-6" />
<nuclide name="B-11" wo="1.68974e-5" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.0197940" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-5" />
<nuclide name="B-11" wo="3.59854e-4" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H-1" wo="0.0358870" />
<nuclide name="O-16" wo="0.2847761" />
<nuclide name="B-10" wo="1.15699e-4" />
<nuclide name="B-11" wo="5.27075e-4" />
<nuclide name="Fe-54" wo="0.02644016154" />
<nuclide name="Fe-56" wo="0.43037146399" />
<nuclide name="Fe-57" wo="0.0101152584" />
<nuclide name="Fe-58" wo="0.00137211607" />
<nuclide name="Ni-58" wo="0.04104621835" />
<nuclide name="Ni-60" wo="0.0163554502" />
<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
<nuclide name="Si-28" wo="0.006234853554" />
<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-5" />
<nuclide name="B-11" wo="2.39272e-4" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-5" />
<nuclide name="B-11" wo="4.30120e-4" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

44
tests/test_score_total_yn/results.py Normal file
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@ -0,0 +1,44 @@
#!/usr/bin/env python
import sys
import numpy as np
# import statepoint
sys.path.append('../../src/utils')
import statepoint
# read in statepoint file
if len(sys.argv) > 1:
sp = statepoint.StatePoint(sys.argv[1])
else:
sp = statepoint.StatePoint('statepoint.10.binary')
sp.read_results()
# extract tally results and convert to vector
results1 = sp.tallies[0].results
shape1 = results1.shape
size1 = (np.product(shape1))
results1 = np.reshape(results1, size1)
results2 = sp.tallies[1].results
shape2 = results2.shape
size2 = (np.product(shape2))
results2 = np.reshape(results2, size2)
# set up output string
outstr = ''
# write out k-combined
outstr += 'k-combined:\n'
outstr += "{0:12.6E} {1:12.6E}\n".format(sp.k_combined[0], sp.k_combined[1])
# write out tally results
outstr += 'tally 1:\n'
for item in results1:
outstr += "{0:12.6E}\n".format(item)
outstr += 'tally 2:\n'
for item in results2:
outstr += "{0:12.6E}\n".format(item)
# write results to file
with open('results_test.dat','w') as fh:
fh.write(outstr)

212
tests/test_score_total_yn/results_true.dat Normal file
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@ -0,0 +1,212 @@
k-combined:
9.785262E-01 2.895177E-02
tally 1:
0.000000E+00
0.000000E+00
1.094646E+01
2.428429E+01
2.225169E+00
1.016830E+00
3.150587E+01
2.052037E+02
tally 2:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.094646E+01
2.428429E+01
5.846652E-02
4.670734E-02
1.274633E-01
5.689843E-03
-2.769645E-01
3.469519E-02
-9.770271E-02
2.212600E-02
-1.718138E-03
6.195671E-03
5.293044E-02
1.357406E-02
-4.557967E-01
5.262731E-02
-5.968883E-02
3.239875E-02
5.152732E-02
5.322314E-03
-4.737115E-02
2.543009E-03
-4.137677E-02
7.737200E-03
2.349356E-01
3.675562E-02
-2.118782E-01
2.259914E-02
9.771726E-02
7.657338E-03
-1.425459E-01
6.661165E-03
5.503163E-02
3.547136E-03
-2.043861E-02
6.938007E-03
9.716884E-02
7.890404E-03
4.580386E-02
1.770664E-03
9.386179E-02
1.633861E-02
-1.267384E-01
1.875299E-02
1.489661E-01
1.033285E-02
-1.653923E-02
4.659923E-03
-7.241633E-02
6.087112E-03
2.225169E+00
1.016830E+00
-3.287201E-02
3.113510E-03
5.276917E-02
2.373544E-03
-3.047290E-02
2.066181E-03
-2.215745E-02
1.448141E-03
-3.197517E-03
1.029606E-03
3.785832E-02
5.476722E-04
-7.694649E-02
2.322476E-03
-1.318499E-02
1.294712E-03
3.252651E-02
7.647996E-04
-8.446605E-03
2.396205E-04
-2.387179E-02
5.981366E-04
4.490141E-02
9.076461E-04
-5.073474E-02
1.479816E-03
2.337733E-03
3.629619E-04
-1.592142E-02
1.932660E-04
2.817351E-02
2.756714E-04
-7.179521E-03
2.705344E-04
5.563912E-03
5.688500E-04
2.382506E-02
2.909462E-04
1.753681E-02
6.909020E-04
-2.592268E-02
3.202222E-04
2.160865E-02
9.134735E-04
-4.319667E-03
7.902430E-04
1.070167E-02
2.288415E-04
3.150587E+01
2.052037E+02
-1.508479E-01
3.017029E-01
1.402160E-01
7.296606E-02
-6.067590E-01
1.366120E-01
-4.674088E-01
1.052625E-01
4.292988E-02
1.212020E-01
-8.705007E-02
7.120546E-02
-4.832242E-01
9.504346E-02
-1.625084E-01
1.004166E-01
7.545226E-02
5.868337E-02
-6.752172E-03
3.870347E-02
-3.514281E-01
7.616059E-02
5.581075E-01
1.419356E-01
-4.187866E-01
5.601005E-02
2.708391E-01
6.304397E-02
4.343467E-02
7.332731E-02
-3.196333E-02
1.037211E-02
-1.138408E-03
2.321733E-02
6.915075E-02
2.899777E-02
4.666937E-02
2.139001E-02
2.022369E-01
7.382740E-02
-1.274694E-01
1.226053E-02
3.724451E-01
1.421241E-01
1.587808E-01
7.967636E-02
-8.004346E-03
4.594356E-02

19
tests/test_score_total_yn/settings.xml Normal file
View file

@ -0,0 +1,19 @@
<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

14
tests/test_score_total_yn/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="10 21 22 23" />
<scores>total</scores>
</tally>
<tally id="2">
<filter type="cell" bins="10 21 22 23" />
<scores>total-y4</scores>
</tally>
</tallies>

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tests/test_score_total_yn/test_score_total_yn.py Normal file
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#!/usr/bin/env python
import os
from subprocess import Popen, STDOUT, PIPE, call
import filecmp
import glob
from optparse import OptionParser
parser = OptionParser()
parser.add_option('--mpi_exec', dest='mpi_exec', default='')
parser.add_option('--mpi_np', dest='mpi_np', default='3')
parser.add_option('--exe', dest='exe')
(opts, args) = parser.parse_args()
cwd = os.getcwd()
def test_run():
if opts.mpi_exec != '':
proc = Popen([opts.mpi_exec, '-np', opts.mpi_np, opts.exe, cwd],
stderr=STDOUT, stdout=PIPE)
else:
proc = Popen([opts.exe, cwd], stderr=STDOUT, stdout=PIPE)
print(proc.communicate()[0])
returncode = proc.returncode
assert returncode == 0, 'OpenMC did not exit successfully.'
def test_created_statepoint():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
assert len(statepoint) == 1, 'Either multiple or no statepoint files exist.'
assert statepoint[0].endswith('binary') or statepoint[0].endswith('h5'),\
'Statepoint file is not a binary or hdf5 file.'
def test_output_exists():
assert os.path.exists(os.path.join(cwd, 'tallies.out')), 'Tally output file does not exist.'
def test_results():
statepoint = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
call(['python', 'results.py', statepoint[0]])
compare = filecmp.cmp('results_test.dat', 'results_true.dat')
if not compare:
os.rename('results_test.dat', 'results_error.dat')
assert compare, 'Results do not agree.'
def teardown():
output = glob.glob(os.path.join(cwd, 'statepoint.10.*'))
output.append(os.path.join(cwd, 'tallies.out'))
output.append(os.path.join(cwd, 'results_test.dat'))
for f in output:
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
# test for openmc executable
if opts.exe is None:
raise Exception('Must specify OpenMC executable from command line with --exe.')
# run tests
test_run()
test_created_statepoint()
test_output_exists()
test_results()
teardown()